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Nine Mile Point Unit 2 - Final Operating Exam (Sections a, B, and C) Folder 3)
	ML14076A123
Person / Time
Site:	Nine Mile Point
Issue date:	02/26/2014
From:	; Exelon Generation Co
To:	Fish T H, Brian Fuller; Operations Branch I
	Jackson D E
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ML13295A030	List: ML14059A010; ML14059A254; ML14059A255; ML14059A256; ML14059A258; ML14076A120; ML14076A121; ML14076A122; ML14076A123;
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CENG" NINE MILE POINT NUCLEAR STATION . Training Id: 2013 NRC Simulator S-1 Revision:

1.0 -----Title: Rotate Drywell Unit Coolers (Alternate Path) Approvals:

Signature I Printed Name Developed By David Huff 01/29/2014 Validated By Jason Saw er 12/03/2013 Facility Reviewer 15 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

Date: JPM S-1 Page 1 of 9 NRC March 2014

a JOint venture of---,

-;:,eoF NINE MILE POINT NUCLEAR STATION References

1. N2-0P-60, Drywell Cooling 2. N2-ARP-873200 JPM S-1 Page 2 of 9 NRC March 2014

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I NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to rotate the Drywell Unit Coolers 3A and B and respond to a degraded condition on Unit Cooler 3B b. This JPM is considered alternate path because once the unit coolers have been rotated, the operator will receive indication that the unit cooler placed in service has degraded.

The operator will be required to respond per the applicable ARP and place the previously running unit cooler back in service and place in pull to lock the degraded unit cooler. 2. Task Information:

a. N2-223004-01002, Rotate Drywell Unit Coolers 3A and 3B b. K/A 223001, A4.12 (3.5/3.6)

3. Evaluation I Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical .Task No Altern Path. Yes LOD >1.0 Yes 4. Recommended Start Location a. Unit 2 Simulator JPM S-1 Page 3 of 9 NRC March 2014

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I NINE MILE POINT NUCLEAR STATION 5. Simulator Setup (if required)

a. This JPM can be performed in Mode 1, 2, or 3 as long as power is available to both Unit Coolers 3A and 8 b. Ensure Drywell Unit Cooler 3A is running and 38 is secured c. Set Malfunction PC36B, DW Unit Cooler 38 Vibration High on Trigger 1 with a 3 second delay. d. Set the following Event Trigger on Event 1: Event Action: HZLCW2CCPMOV3A(1)==1 .AND. HZLPC1DRSB03(2)==1 Command: Blank

Description:

2CCP-MOV3A Green Light On and UC38 Red Light On 6. JPM Setup (if required)

a. Prepare a copy of N2-0P-60, Section 2.0. Include a copy of the Precautions and Limitations.

No steps need to be marked up. b. If this JPM is run multiple times, ensure ARP 873214 is erased after each JPM. JPM S-1 Page 4 of 9 NRC March 2014 CENG .. a pet 'ectvm of I 0 NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM S-1 Page 5 of 9 NRC March 2014 CENG .. 8J01ntventure ol---

NINE MILE POINT NUCLEAR STATION INITIAL INITIATING CUE .START TIME Given:

The plant is in Mode 1

2DRS-UC3A is running and 2DRS-UC3B is in standby

Unit Coolers 3A and 3B need to be rotated to equalize runtime Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Rotate Drywe/1 Unit Coolers by starting 2DRS-UC3B and stopping 2DRS-UC3A in accordance with N2-0P-60, Section F.2.0 PERFQRMA.NCE ACT. CODE EVALUATOR P/S/NA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used lAW CNG-OP-1.01-2001, Communications and Briefings.

2. Obtain a copy of N2-0P-60 and review I p SAT I UNSAT utilize the correct section of the procedure STD: Current version of N2-0P-60 obtained and section F.2.0 reviewed lAW CNG-PR-2.01-1000, Document Control.

2DRS-UC3A and UC3B should be rotated occasionally to equalize ProcecJure' NOte! operating time and equipment wear. .* ***

All control switches and indicating lights are located on 2CEC*PNL873, unless otherwise noted. 3. Open CCP-MOV3B (3A), UNIT COOLER 3B p *PM,S/FAIL

(3A) RBCLC INLET to the standby unit cooler. STD: PJaees C(;t>*HOV38 switch to OPEN at 2CB;*PNL873.

JPM S-1 Page 6 of 9 NRC March 2014

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j NINE MILE POINT NUCLEAR STATION PERFORMANCE

..

4. Start standby unit cooler DRS-UC3B (UC3A) 5. Stop DRS-UC3A (UC3B) by placing control switch to STOP ACT. CODE PIS INA p p EVALUATOR

,. *PASSl.FAtL

' ' ' ' ' / . *, ' . ' .. .. observes,the RED running light is lit and the GREEN off. light is not fit; * . ' *PASS/ FAIL.

to STOPat'2CEC*PNL873 and observ'es tile RED dtniurig light is not fit and the off

light islit, Two seconds after completion of the following step, a high vibration condition will occur on 2DRS-UC3B.

The operator will reference ARP 873214 which will direct restarting UC3A and placing in Pull To Lock UC3B 6. 7. 8. 9. JPM S-1 Close CCP-MOV3A (3B), UNIT COOLER 3A (3B) RBCLC INLET to the standby unit cooler. Recognizes and reports Annunciator 873214 in alarm References ARP for 873214 IF 2DRS-UC3A, UNIT COOLER is available, PERFORM the following:

Open CCP-MOV3A, UNIT COOLER 3A RBCLC INLET. Page 7 of 9 p p p p ' *PASS I FAIL STD:

C.CP-;MOV3A .switch to CLOSE at 2CEC*PNL873.

SAT I UNSAT STD: Proper alarm response used lAW CNG-OP-1.01-2003, Alarm Response and Control. SAT I UNSAT STD: Determines 2DRS-UC3A is available.

PASS./ FAIL STD:.Piaces.{XP:+t()V3A

switch to OPEN at2CEC*PNI..873.

NRC March 2014 CENG .. a JOint venture of---, o=---;;,eDF I NINE MILE POINT NUCLEAR STATION

' 10.

Start 2DRS-UC3A

11.

STOP 2DRS-UC3B by placing control switch in PULL TO LOCK 12.

CLOSE CCP-MOV3B, UNIT COOLER 38 RBCLC INLET ACT. CODE P/5/NA p p p EVALUATOR STD: Placte5: PRS*UC$A SWitch to STAfl.tai2CEC*P/Vf.873 and 'EDrunl1i11g .light is lit.,nd the GREEN off Hght is not lit.. > * *PASS I FAIL to.PULL TO t'QSK at 2CEC*fJNL873 aild Observes .the RED running light is lit. and the .GREEN offlight is lit. . . *,' ., ,! ** *' ' I , SAT/ UNSAT STD: Places CCP-MOV3B switch to CLOSE at 2CEC*PNL873.

Once CCP-MOV3B is closed, provide the following Cue: I ST()PTIME JPM S-1 Cue: Your task is complete, another operator will complete the remainder of the ARP actions. CCP-MOV3B is closed. Page 8 of 9 NRC March 2014

aJOI'""II venture of----, 0=.:;-n -f'eoF I NINE MILE POINT NUCLEAR STATION lNil"IAt..

'coNDITIONS CUE JPM S-1 JPM Handout Given:

The plant is in Mode 1

2DRS-UC3A is running and 2DRS-UC3B is in standby

Unit Coolers 3A and 3B need to be rotated to equalize runtime Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Rotate Drywe/1 Unit Coolers by starting 2DRS-UC3B and stopping 2DRS-UC3A in accordance with N2-0P-60, Section F.2.0 Page 9 of 9 NRC March 2014 CENG -------*--*

-* 1 O Conateitlltlon

,.,ot..,eDF i .,/11,' -*-------**-

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l NINE MILE POINT NUCLEAR STAI"ION Training Id: 2013 NRC Simulator S-2 Revision:

1.08 Title: Perform RPS Weekly Surveillance (Alternate Path) Approvals:

Signature I Printed Name Developed By David Huff 01/29/2014 Validated By Mark Rushmore 01/31/2014 Facility Re.viewer Appr 20 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

Date: JPM S-2 Page 1 of 13 NRC March 2014 CENG .. a]Ointventureol--

0=---

I NINE MILE POINT NUCLEAR STATION References

1. N2-0SP-RPS-W002, Manual Scram Channel Functional Test 2. N2-SOP-08, Unplanned Power Changes JPM S-2 Page 2 of 13 NRC March 2014 CENG .. a jOint ventureof--

NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to perform the RPS Weekly Surveillance.

b. This JPM is considered alternate path because when the scram test is performed, three control rods will individually scram. The operator will be required to enter N2-SOP-08 and place the Mode Switch in Shutdown.

2. Task Information:

a. N2-212000-01029, Perform N2-0SP-RPS-W002, Manual Scram Channel Functional Test b. K/A 212000, A2.02 (3.6/3.7)

3. Evaluation I Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical Task No Alternate Path Yes LOD >1.0 Yes 4. Recommended Start Location a. Unit 2 Simulator

5. Simulator Setup (if required)

a. This JPM should be performed in Mode 1 JPM S-2 Page 3 of 13 NRC March 2014 a JO'nt 'entum ol I -J,eOF NINE MILE POINT NUCLEAR STATION b. Ensure that both RPS A and B are reset c. Set Malfunctions RD09-10-39, RD09-54-27, and RD09-34-07, Control Rod Scram on Trigger 1 (or other trigger if doing this JPM in conjunction with another JPM). d. Set the following Event Trigger on the same trigger you set the above malfunctions in: Event Action: ZDRPS3DP(3)==1 Command: Blank

Description:

A2 Manual Scram Pushbutton Depressed.

6. JPM Setup (if required)

a. Prepare a copy of N2-0SP-RPS-W002.

Mark up Section 7.0. The operator will only be performing testing on RPS A and C channels, so N/A the remaining sections of B and D. b. If the JPM is to be run multiple times, make sufficient copies of the marked up procedure to run them. JPM S-2 Page 4 of 13 NRC March 2014 CENG .. a JO"I ventuce ot I NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM S-2 Page 5 of 13 NRC March 2014 a jOint venture of*---, 0=:-" -],eo* I NINE MILE POINT NUCLEAR STATION INI'nAL CONDITIONS INITIATING CUE START TIME Given:

The plant is in Mode 1

Maintenance has just been completed on RPS A1 and A2

Post Maintenance testing is required for RPS Channels A1 and A2

Communications have been established between 2CEC*PNL603 and 2CEC*PNL609 Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Perform a Manual Scram Channel Functional Test on RPS Channel A and C in accordance with N2-0SP-RPS-W002, Section 8.2 and 8.3 Cue: Provide the marked up copy of N2-0SP-RPS-W002 to the operator.

PERFORMANCE ACT. CODE EVALUATOR P/5/NA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used lAW CNG-OP-1.01-2001, Communications and Briefings.

2. Reviews marked up copy of N2-0SP-RPS-p SAT I UNSAT W002 and utilizes the correct section of the procedure STD: N2-0SP-RPS-W002 is reviewed lAW CNG-PR-2.01-1000, Document Control. l > {;"" *< .

All indicators and controls for this test are located on panel 2CEC*PNL603 unless otherwise specified.

3. Verify that there is NO half scram on the "B" p SAT I UNSAT side. STD: Observes the four white RPS B power lights are lit on 2CEC*PNL603.

JPM 5-2 Page 6 of 13 NRC March 2014 CENG .. a )O"t 'entuce of I o=-lon NINE MILE POINT NUCLEAR STATION PERFORMANCE

4. Notify CRO that a half scram on "A" side will be generated.

Cue: As the CRO, acknowledge the report of a half scram on the A side. ACT. CODE PI Sf NA p EVALUATOR SAT I UNSAT STD: Proper communications used lAW CNG-OP-1.01-2001, Communications and Briefings.

The operator may choose to perform the actions for an Expected Annunciator which involves informing the CRS and reviewing the associated ARP. As the Evelluator Evaluator, and as necessary, during the course of this JPM, acknowledge the 1 Note: Expected or Actual Annunciators as the CRS. Additionally at your discretion you may choose to inform the operator that all further notifications for Expected 1.>' ',' } 5. 6. 7. 8. Annunciators are not required.

Arm the REACTOR SCRAM A1 pushbutton Verify annunciator 603113, RPS A MANUAL SCRAM SWITCH ARMED, has alarmed. Depress AND hold for 2 to 3 seconds the REACTOR SCRAM A1 pushbutton.

Verify the following annunciators have alarmed:

603110, RPS A AUTO TRIP

603111, RPS A MANUAL TRIP JPM S-2 Page 7 of 13 p p p p *PASS I J=AIL STD: Rotates tl)e REACTOR SCRAM Al COLLAR to the ARMED.(X>Sition.

SAT I UNSAT STD: Observes Annunciator 603113 illuminated.

May depress the 2CEC*PNL603 annunciator SILENCE and ACKNOWLEDGE BUTTONS. *PAS$/ FAIL STD: Depresses the SCRAM A1 PUSHBU7TON for 2 to 3 seconds. SAT I UNSAT STD: Observes Annunciators 603110 and 603111 illuminated.

Depresses the 2CEC*PNL603 annunciator SILENCE and ACKNOWLEDGE BUTTONS. NRC March 2014 a JO"t 'entuce of I NINE MILE POINT NUCLEAR STATION PERFORMANCE

9. Verify the status of the following indicating lights:

REACTOR SCRAM TRIP LOGIC A1 on 2CEC*PNL609 is extinguished.

Cue: REACTOR SCRAM TRIP LOGIC A1 on 2CEC*PNL609 is extinguished.

PILOT SCRAM VALVE SOLENOIDS A, C, E, AND G are extinguished.

10. Reset the REACTOR SCRAM RESET LOGIC A. ACT.COOE EVA.LUATOR P/S/NA p SAT/ UNSAT STD: Observes the four white pilot lights on 2CEC*PNL603 for RPS A not lit. p S'TD: Rotates the .REACTOR SCRAM RESET i.oGIC A control switch to the $ET' position.

.. If the Plant Computer Printouts and/or Sequence of Events do not print out the

... right computer points, then provide a cue as necessary to indicate to the **'NC,tef*

candidate that all required computer points are in. t> 11. Verify the following occurred for the tripped p SAT I UNSAT condition:

Verify the following Plant Computer STD: Observes on the Plant

Printouts:

Process Computer, Computer Points RPSUC01 and 03 are in 0 RPSUC01, RPS A MANUAL TRIP, the TRIPPED condition.

TRIPPED 0 RPSUC03, RPS A AUTO TRIP, TRIPPED 12.

Verify the following Sequence of Events p SAT I UNSAT Printouts:

RPSUC01, RPS A MANUAL TRIP, STD: Observes on the 0 TRIPPED Sequence of Events Printouts, Computer Points RPSUC01 and 0 RPSUC03, RPS A AUTO TRIP, 03 are in the TRIPPED TRIPPED condition.

JPM S-2 Page 8 of 13 NRC March 2014 CENG .. a JO<OI venluce ol I NINE MILE POINT NUCLEAR STATION PERFORMANCE

13. Verify the following alarms AND indications for the reset condition:

Verify the following alarms AND indications for the reset condition:

0 603110, RPS A AUTO TRIP 0 603111, RPS A MANUAL TRIP 14.

Verify the following Plant Computer Printouts:

0 RPSUC01, RPS A MANUAL TRIP, ALRMCLR 0 RPSUC03, RPS A AUTO TRIP, ALRMCLR 15.

Verify the following Sequence of Events Printouts:

0 RPSUC01, RPS A MANUAL TRIP, ALRMCLR 0 RPSUC03, RPS A AUTO TRIP, ALRMCLR 16. Verify the status of the following indicating lights:

REACTOR SCRAM TRIP LOGIC A1 on 2CEC*PNL609 is ILLUMINATED.

Cue: REACTOR SCRAM TRIP LOGIC A1 on 2CEC*PNL609 is ILLUMINATED.

PILOT SCRAM VALVE SOLENOIDS A, C, E, AND G are illuminated.

17. Disarm the REACTOR SCRAM A1 pushbutton JPM S-2 Page 9 of 13 ACT. CODE EVALUATOR P /5/NA p SAT I UNSAT STD: Observes Annunciators 603110 and 603111 clear. Depresses the 2CEC*PNL603 annunciator SILENCE, ACKNOWLEDGE, and RESET BUTTONS. p SAT I UNSAT STD: Observes the Plant Process Computer, Computer Points RPSUC01 and 03 are shown in the ALRMCLR condition.

p SAT I UNSAT STD: Observes on the Sequence of Events Printouts, Computer Points RPSUC01 and 03 are in the ALRMCLR condition.

p SAT I UNSAT STD: Observes the four white pilot lights on 2CEC*PNL603 for RPS A lit. p *PASs/fAIL STD: Rotatfi!S the SCRAMA1)COif..i4if£r;the . DISARME,D NRC March 2014 3JOtnt venture of-----,

-;;,eoF I NINE MILE POINT NUCLEAR STATION .PERFORMANCE

18. Verify annunciator 603113, RPS A MANUAL SCRAM SWITCH ARMED, is extinguished.

ACT. CODE P/S/NA p EVALUATOR SAT I UNSAT STD: Observes Annunciator 603113 not lit. Depresses the 2CEC*PNL603 annunciator SILENCE, ACKNOWLEDGE, and RESET BUTTONS. Proe.Jure Note:.* All indicators and controls for this test are located on panel 2CEC*PNL603 unless otherwise specified.

19. Verify that there is NO half scram on the "B" side. 20. Notify CRO that a half scram on "A" side will be generated.

Cue: As the CRO, acknowledge the report of a half scram on the A side. 21. Arm the REACTOR SCRAM A2 pushbutton

22. Verify annunciator 603113, RPS A MANUAL SCRAM SWITCH ARMED, has alarmed. p p p p SAT I UNSAT STD: Observes the four white RPS B power lights are lit on 2CEC*PNL603.

SAT I UNSAT STD: Proper communications used lAW CNG-OP-1.01-2001, Communications and Briefings.

PASS l FAIL. STD: Rotates the REAc:T'OR SCRAM A2 to the ARMED position.

SAT I UNSAT STD: Observes Annunciator 603113 illuminated.

May depress the 2CEC*PNL603 annunciator SILENCE and ACKNOWLEDGE BUTTONS. Afterrilltt!

/ .

.* ', Once the operator depresses the REACTOR SCRAM A2 pushbutton, three control rods will scram. The operator will respond per N2-SOP-08 and place the Mode Switch to Shutdown.

JPM S-2 Page 10 of 13 NRC March 2014 CENG .. ajolnl venture of---, 0=:'"'....

<t,eDF I NINE MILE POINT NUCLEAR STATION 23. 24. PERFORMANCE Depress AND hold for 2 to 3 seconds the REACTOR SCRAM A2 pushbutton.

Recognizes using the Rod Worth Minimizer, Full Core Display, and/or the Plant Process Computer that three control rods Drifted/Scrammed.

Cue: If necessary as the CRS, acknowledge the report of three drifting/scrammed control rods. ACT. CODE P/S/NA p p EVALUATOR . . *PA.$5! FAIL STD(Depresses th(! REACTOR. sCRAf-( A2 PVSH8U1TON

.. to 3 seconds. . . SAT I UNSAT STD: Using the RWM, Full Core display, and/or PPC, determines that three rods have drifted and/or scrammed by observing the drifting control rod message on the RWM and/or three RED DRIFT/SCRAM LIGHTS on the Full Core Display are lit and/or reviewing the PPC Rod display to check for drifting control rods. I> ""' ' I**** The operator may or may not refer to N2-SOP-08 prior to taking the next action. Either action is acceptable.

Additionally, due to the immediate action requirement of N2-SOP-08 to place the mode switch to shutdown based on more than one rod drifted or scrammed, attempts to refer to the ARP for required actions or delaying placing the mode switch in shutdown for an unreasonable amount of time should not occur. If the operator refers to the Rod Drift or Accumulator Trouble ARP or delays placing the Mode Switch to Shutdown for an unreasonable amount of time, then Step 25 should be graded as FAIL. 25. Places the Mode Switch to Shutdown.

Cue: If necessary, as the CRS, acknowledge entry into N2-SOP-08 and Scram Report ., .. **.*** *. p *PASS/.FAIL STD:.Piai:es the Mode Switch to the Shutdown Position.

Observes that the rea.ctor:

scrams and all rods insert. Evaluator l*>:::.t;t***

Once the Mode Switch is in Shutdown, provide the following cue: Cue: Your task is complete, another operator wi/1 complete any remaining actions. JPM S-2 Page 11 of 13 NRC March 2014 CENG,. 8J01ntventureo1---

0=:"atlon

-:,eDF NINE MILE POINT NUCLEAR STATION I I Mode Switch to Shutdown.

I sTOPTIME JPM S-2 Page 12 of 13 NRC March 2014 a pnt ventuce ot I -::,eDF NINE MILE POINT NUCLEAR STATION trunAL* CONDifiOHS INITIATING*

CU.E JPM S-2 JPM Handout Given:

The plant is in Mode 1

Maintenance has just been completed on RPS A1 and A2

Post Maintenance testing is required for RPS Channels A1 and A2

Communications have been established between 2CEC*PNL603 and 2CEC*PNL609 Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Perform a Manual Scram Channel Functional Test on RPS Channel A and C in accordance with N2-0SP-RPS-W002, Section 8.2 and 8.3 Cue: Provide the marked up copy of N2-0SP-RPS-W002 to the operator.

Page 13 of 13 NRC March 2014 CENG. NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC Simulator S-3 Revision:

0.0 --=...:...=....

__ _ Title:

Control Rod Drive Flow (Alternate Path) Approvals:

Signature I Printed Name Developed By David Huff 12/18/2013 Validated By Jason Sawyer 12/03/2013 Facility Reviewer (', (\. ... ..)6..._ "' Aaron Armstrong

'/., lza1 I I Approximate Duration:

10 minutes Documentation of Performance:

Performer:

Evaluator::

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comment?:

Evaluators Signature:

Date: JPM S-3 Page 1 of 12 NRC March 2014 CENG .. a)Ointventureof---

0=::-.. lon -:,*,eoF NINE MILE POINT NUCLEAR STATION References

1. N2-0P-30, Control Rod Drive 2. N2-EOP-RPV, RPV Control JPM S-3 Page 2 of 12 NRC March 2014 aJ01'1tventureo1--

o=-

I NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to Maximize RDS Flow after a reactor scram as well as respond to a high suction strainer differential pressure.

b. This JPM is considered alternate path because once RDS flow is maximized, a high suction strainer differential pressure alarm will occur. The operator will be required to recognize the degraded condition and take conditional steps to mitigate it in accordance with the operating procedure.

2. Task Information:

a. N2-201001-01012, Respond to Annunciator 603318, CRD PUMPS SUCTION FLTR DIFF PRESSURE HIGH b. K/A 201001, A2.06 (2.9/2.9)

3. Evaluation I Task Criteria Evaluation Method . ;,;,;.;P . . :, . . . . .... * : Perform ... ' ...*....

.*. . !;valuation Location Simulator

. nme.Critical Task No Yes Yes 4. Recommended Start Location a. Unit 2 Simulator JPM 5-3 Page 3 of 12 NRC March 2014 CENG .. a totnt 'entuo; of I NINE MILE POINT NUCLEAR STATION 5. Simulator Setup (if required)

a. Prepare the simulator as follows: 1) Snap to any full power IC 2) Ensure RDS Pump lA is running and Pump lB is in standby. 3) Place HPCS in PTL 4) Trip the RCIC Turbine 5) Insert malfunctions FW01A, B, and C (Condensate Pump Trip) to remove the condensate pumps from service. 6) Allow the Feed Pumps to trip and level to lower to the scram setpoint.

7) Once the Reactor has scrammed, place the mode switch to shutdown.

8) Allow RPV level to stabilize out between 100 and 150 inches and house loads to transfer to Lines 5 and 6. b. Set Malfunction AN603318, CRD PUMPS SUCTION FLTR DIFF PRESSURE HIGH, FV=CRY WOLF on Trigger 1 with a 2 second time delay c. Set the following Event Trigger on Event 1: Event Action: HZLRDF003(2)==1 .AND. HZLRDF003(1)==0 Command: Blank

Description:

2RDS-PV101 Red Light On and Green Light Off (PV101 is fully open). JPM S-3 Page 4 of 12 NRC March 2014 CENG .. BJOintventureol--

NINE MILE POINT NUCLEAR STATION 6. JPM Setup (if required)

a. Prepare a copy of N2-0P-30, Section 3.0. Include a copy of the Precautions and Limitations.

No steps need to be marked up. b. Have a yellow sticky available with the following computer point written on it indicating it is in alarm: RDSPC06, CRD PMPS SUCT FLT D/P. JPM S-3 Page 5 of 12 NRC March 2014 CENG .. ajolnlventure of--0 =:.uon -;:,eDF : NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM S-3 Page 6 of 12 NRC March 2014

a iDinl venture ot I NINE MILE POINT NUCLEAR STATION .:trttiUt..

... * ... :c-tJirib,J!$., . " ;

.. r:: * ., , , ., *. *.*INITIATIN.G

., *,cue*****

Given:

The plant has scrammed due to a loss of all condensate pumps

The mode switch is in shutdown

HPCS and RCIC are unavailable.

The crew is executing N2-EOP-RPV, RPV Level Control Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Maximize RDS Flow per N2-0P-30, Control Rod Drive, Section H.3.0 PERFORMANCE PI S/NA .EVALUATOR

1. Provide repeat back of initiating cue Cue: Acknowledge repeat back providing correction if necessary.

p SAT I UNSAT STD: Proper communications used lAW CNG-OP-1.01-2001, Communications and Briefings.

2. JPM S-3 Obtain a copy of N2-0P-30 and review I utilize the correct section of the procedure p SAT I UNSAT STD: Current version of N2-0P-30 obtained and section H.3.0 reviewed lAW CNG-PR-2.01-1 000, Document Control. Performance may be required by the EOPs. Changes to this section of the procedure (including renumbering) are required to be reviewed by the EOP Coordinator.

Page 7 of 12 NRC March 2014 CENG .. a JOint venture of----, o=otlon I NINE MILE POINT NUCLEAR STATION PERFQJlMANCE . > '* 3. IF (at any time in this Subsection) annunciator 603318, CRD PUMPS SUCTION FLTR DIFF PRESSURE HIGH, is received; perform the following on RB 215' el.:

Open 2RDS-V2B(A), SUCTION FILTER-1B (A) INLET ISOL

3.1.2 Open 2RDS-V3B(A), SUCTION FILTER-1B (A) OUTLET !SOL

3.1.3 Open 2RDS-V8, FLT.-BYPASS-LINE SUCTION STRAINER ISOL

3.1.4 Open 2RDS-V9, FLT.-BYPASS-LINE SUCTION STRAINER !SOL. 4. IF (at any time in this Subsection) annunciator 603317, CRD DRV WTRIRCS PMP SEAL FILTR DIP HIGH, is received, perform the following on RB 261' el.:

Open 2RDS-v23B(A), DISCH. FLT 2B (A) INLET ISOL.

3.2.2 Open 2RDS-V26B(A), DISCH. FLT . 2B (A) OUTLET ISOL. 5. Verify RPS is tripped per N2-SOP-101C.

6. Verify the following pumps are running (2CEC*PNL603), IF available:

RDS-P1A, CRD PUMP 1A JPM S-3 Page 8 of 12 ACT. CQDE EVALUATOR P/ S/ NA p SAT I UNSAT STD: Observes that Annunciator 603318 is not lit and determines that this step is not applicable at this time . p SAT I UNSAT STD: Observes that Annunciator 603317 is not lit and determines that this step is not applicable at this time . p SAT I UNSAT STD: Observes the eight white scram solenoid power lights for RPS A and B are not lit on 2CEC*PNL603 p SAT I UNSAT STD: Determines RDS-P1A is already running by observing the control switch is in Normal After Start (red flagged) and amps are indicated on the amp meter on 2CEC*PNL603.

NRC March 2014 a jo"t vectuce of I NINE MILE POINT NUCLEAR STATION 7. 8. 9. JPM S-3

RDS-P1B, CRD PUMP 18 Place 2RDS-FC107, CRD FLOW CONTROL, in MANUAL (2CEC*PNL603).

ACT. CODE* P /S/NA p p EVALUATOR STD: Places corittor *' * ., ....

011.

the

** . . .**. ' 2C;EC*PNL'603.

To prevent pump motor damage or tripping the supply breaker, RDS pump motor current shall not exceed 40 amps. RDS P1A and B amps should be tv23 amps. After performance of this step, amps should rise to tv27 amps. Open 2RDS-FC107 UNTIL RDS pump motor current(s) approach 40 amps OR controller output meter is 100% (2CEC*PNL603).

oPEl( **.* . . J,*

.:* .*. * * . Observesl:h/Jt aniPsior.P1A andadoitoi:

.40 .* am{JS. Two seconds after completion of the following step, Annunciator 603318 will alarm. The operator will reference Step H.3.1 to mitigate the event At the completion of the below step, RDS-P1A and B amps should be tv28 amps. Page 9 of 12 NRC March 2014 CENG .. a JO<Ct vectu'e ot I NINE MILE POINT NUCLEAR STATION PERFC)JtMANCE

10. IF NOT driving control rods, open PV101, DRIVE WTR PRESS CONTROL MOV, UNTIL RDS pump motor current(s) approach 40 amps OR fully open (2CEC*PNL603).

11. Recognize Annunciator 603318 is in alarm. Cue: If the operator attempts to check which computer point is in alarm on the plant process computer, place the yellow sticky with the computer point number on the computer screen. Cue: If required, as CRS acknowledge report of annunciator.

Direct the operator to "Respond per the appropriate procedure".

ACT.COOE P/5/NA EVALUATOR SAT/ UNSAT STD: Observes 603318 annunciator tile is lit. May depress the silent and acknowledge pushbuttons.

May report annunciator to CRS. The next critical step may be performed in multiple ways. The operator may choose to contact a PO and direct them to perform N2-0P-30, Step H.3.1 -or-the operator may choose to direct the PO to perform each step individually.

Either method is acceptable.

The critical aspect of the below step is that the operator recognize that step H.3.1 is now applicable and direct action in accordance with the step. It is inappropriate for the operator to enter N2-SOP-30 or the actions of the ARP. If the operator gives the PO direction to simply "Swap suction filters" then this step should be graded as "Fail" 12. References step H.3.1, contacts a Plant Operator, and direct them to perform N2-0P-30, Step H.3.1. JPM S-3 Cue: As PO, acknowledge direction to perform N2-0P-30, Step H.3.1. or acknowledge the individual step Cue: If asked as the PO, inform the operator that Suction Filter A is in service. Page 10 of 12 Step the PO to' stepindivlrJuiJ!Jy.

NRC March 2014 a JO"t venturn ol I NINE MILE POINT NUCLEAR STATION TERMINAttM(i I cuE JPM S-3 .. ACT. CODE PI S/NA . EVAWATOR Once a PO is contacted and directed to perform N2-0P-30, Step H.3.1, give the following cue: Cue: Your task is complete, another operator will complete any remaining actions. A Plant Operator is contacted and directed to perform N2-0P-30, Step H.3.1. Page 11 of 12 NRC March 2014

a JO'n"entuce of I NINE MILE POINT NUCLEAR STATION

..

JPM Handout Given:

The plant has scrammed due to a loss of all condensate pumps

The mode switch is in shutdown

HPCS and RCIC are unavailable.

The crew is executing N2-EOP-RPV, RPV Level Control Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions l"ltiAltNG

**** (Operators Name), Maximize RDS Flow per N2-0P-30, Control Rod Drive, *CUE Section H.3.0 JPM S-3 Page 12 of 12 NRC March 2014 CENG .. NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC Simulator S-4 Revision:

0.0 --=-=-=-----

Title: Reset LV10B Lockout and Place FWLC in Automatic (Alternate Path) Approvals:

Developed By Validated By Facility Reviewer Signature I Printed Name 12/18/2013 Jason Sawyer Aaron Armstrong Approximate Duration:

__ _;;:2;;_;;0_m_in-'u'-t_e_s

__ 12/03/2013 I }A /2.01'-f r 1 Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

_________

_ Date: JPM S-4 Page 1 of 12 NRC March 2014 a JO'" ventuce of I o=-lon -::,eDF NINE MILE POINT NUCLEAR STATION References

1. N2-SOP-06, Feedwater Failures JPM S-4 Page 2 of 12 NRC March 2014

a JO"t 'entuce of I

-;:,eDF NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information 1.

Description:

a. This JPM tests the operator's ability to reset an LV10 lockout and place FWLC in full automatic control. b. This JPM is considered alternate path because once the LV10 is reset and placed back in automatic, the master FWLC controller will fail requiring the operator to place FWLC in manual and restore level to the normal band. 2. Task Information:

a. N2-SOP-06-01001, Respond to SOP-06 Feedwater Failures b. K/A 259001, A4.05 (4.0/3.9)

3. Evaluation I Task Criteria . . .. Evaluation Method Perform * '* c '* v*

Simulator . *. ,. . .*.. . time crttlcal Task ... :*** .. ** .. : :; . -;,.** No Yes Yes 4. Recommended Start Location a. Unit 2 Simulator

5. Simulator Setup (if required)

a. Prepare the simulator as follows: JPM S-4 Page 3 of 12 NRC March 2014 a )O>Ot 'entuce of I NINE MILE POINT NUCLEAR STATION 1) Reset to any full power IC 2) Place LV10B in manual control 3) Adjust LV10B valve position to tv35°/o open 4) Insert Malfunction FW52B, 2FWS-LV10B Lockup 5) Verify the LV10B 86-device has actuated 6) Set LV10B Controller Horizontal Output to tv45°/o 7) Delete Malfunction FW52B 8) Allow plant conditions to stabilize

b. Set Malfunction FW13, FEEDWATER MASTER CONTROLLER FAILURE -HIGH, FV=95°/o, on Trigger 1 with no Delay Time c. Set the following Event Trigger on Event 1: Event Action: HZLC33R601B(2)==1 Command: Blank

Description:

LV10B Controller AUTO Green Indicating Light is ON. 6. JPM Setup (if required)

a. Prepare a copy of N2-SOP-06.

Include a copy of both flow charts marked up to "Restore Valve Control per Attachment 1, Step 1.1.3". Mark up Attachment 1, Steps 1.1.3.a and 1.1.3.b as complete.

JPM 5-4 Page 4 of 12 NRC March 2014

a JO'c1 ventuce of I NINE MILE POINT NUCLEAR STATION B. Read Before Every lPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM S-4 Page 5 of 12 NRC March 2014 CENG .. a JOint venture of 1 NINE MILE POINT NUCLEAR STATION

.. [ START.nME i* 1.) Given:

The plant is at 100% power.

The crew has entered N2-SOP-06, Feedwater Failures due to an LV10B Lockup

The cause of the LV10B Lockup was due to an operator inadvertently bumping a power supply breaker on 2NHS-MCC003

The breaker was inspected for damage and determined to be functioning correctly.

Operators have restored power to LV10B.

The Master FWLC Controller is currently controlling LV10A in automatic with LV10B in manual and locked up at rv35% open

There is no evidence that LV10B is drifting or that Feedwater Pump Limits are being challenged.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions

{Operators Name), Restore LV10B valve control and return LV10B to automatic control per N2-SOP-06, Attachment 1, Step 1.1.3 .*, ..

ACT *. CODE P/S/NA ,, r.", 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used lAW CNG-OP-1.01-2001, Communications and Briefings.

2. Obtain a copy of N2-SOP-06 and review I p SAT I UNSAT utilize the correct section of the procedure STD: Current version of N2-SOP-06 obtained and Attachment 1, Step 1.1.3 reviewed lAW CNG-PR-2.01-1000, Document Control. JPM S-4 Page 6 of 12 NRC March 2014 CENG .. a JOint venture ol 1 NINE MILE POINT NUCLEAR STATION 3. 4. 5. JPM S-4 At 2NHS-MCC003, verify power is available AND breaker is ON:

2NHS-MCC003-7C (2FWS-LV10A)

2NHS-MCC003-21B (2FWS-LV10B)

2NHS-MCC003-14A (2FWS-LV10C)

At 2FWS-PNL10A (B,C), verify circuit breaker is ON Verify affected controller 2FWS-HIC1010A (B, C) in Manual ACT. CODE P/S/M p p SAT I UNSAT STD: Determines these steps are already completed per the provided marked up procedure copy. SAT I UNSAT STD: At 2CEC*PNL603, observes the AMBER manual light is lit and the GREEN auto light is not lit on HIC1010B controller.

If the horizontal output indicator does not match actual valve position, the valve will reposition when the 86 device is reset. Due to the size of the position increments on the LV10B controller, it may be difficult for an evaluator to determine if the valve position and controller outputs are correctly matched per Steps 5 and 10 of this JPM. The evaluator may ask the simulator booth operator to document the exact values shown on the controller as the candidates complete these steps. The evaluator may then use these values to assist in grading of these steps. See the Evaluator Job Aide at the end of this JPM for additional information.

Set 2FWS-HIC1010A (B,C) output (horizontal) to match actual valve position Page 7 of 12 p

' ', NRC March 2014 CENG_ a jOint venture ol------, 0=:--],eoF I NINE MILE POINT NUCLEAR STATION 6. 7. 8. 9. Verify Annunciator 603143 is clear (within dead band) At panel 603, reset 86 device (Control signal reset) IF desired, return valve to automatic control as follows:

IF a single feed pump is in service, restore control to automatic per N2-0P-3, F.8.4 ACT.cooe*

P/SJNA. p p p p .

Steps 10 and 11 may be performed concurrently.

10. JPM S-4

Using OPEN/CLOSE detent pushbuttons on 2FWS-HIC1010A (B, C) controller, throttle 2FWS-LV10A (B, C), Feedwater Pump 1A (B, C) Level Control Valve, UNTIL input signal (vertical)

AND output signal (horizontal) on 2FWS-HIC1010A (B, C) controller are matched Page 8 of 12 p SAT/ UNSAT STD: At 2CEC*PNL603, observes Annunciator 603143 not lit. . ..

/ .

teiet SAT/ UNSAT STD: Per the provided initiating cue determines it is desired to return the valve to automatic control. SAT/ UNSAT STD: At 2CEC*PNL852, observes that two feed pumps are running and determines this step is not applicable . NRC March 2014 CENG .. a JO"t vectuce ol I NINE MILE POINT NUCLEAR STATION ACT. CODE P/5/NA **EVALUATOR*

11.

Verify unaffected valve responds to p SAT I UNSAT 12. 13. JPM S-4 control level STD: At 2CEC*PNL603, observes that L V1 OA position indication responds to control RPV water level. After completion of the next step, the Master FWLC Controller will fail causing RPV water to rise. The operator will take manual control of the FWLC system to mitigate the event.

Place 2FWS-LV10A (B, C) in Auto by momentarily depressing Auto (A) pushbutton on 2FWS-HIC1010A (B, C) controller Observe RPV Level is Rising Cue: As necessary, respond as the CRS to reports of rising RPV water level. Direct the operator to "Respond per the appropriate procedure".

p p STD: At 2CEC!IePNL6Q3, depresses .

..

ancl#fe*GJ!i.EEN

Wto light lit. 0' j, < ,?*-**'

,, SAT I UNSAT STD: At 2CEC*PNL603, observes that RPV level is rising. There are several methods available to mitigate this event. The most likely action to take by the operator would be to place the FWLC Master Controller in MANUAL and control level manually.

However, the operator may also choose to place LV10B back in MANUAL control and attempt to control level using the OPEN/CLOSE pushbuttons.

This is an acceptable action but it may also cause the operator to have to place LV10A in MANUAL as well. In the end, the critical aspect of the below steps is to take MANUAL control of the FWLC system and control level to prevent a Level 3 or 8 trip -and-to prevent a trip of either feed pump due to runout/low suction conditions.

Page 9 of 12 NRC March 2014 apnt ""ntuceot 1 ... ion NINE MILE POINT NUCLEAR STATION ACT. CODE P/SINA EVALUATOR

14. Place FWLC system in MANUAL p *;J, :. , " 15. Manually operate the FWLC System and restore RPV water level to normal band. p .*.

..

'

.. TERMINATING

.cU£' ,,;;"-",'*, >': JPM S-4 ] At the evaluator's discretion, after the operator has demonstrated that he has adequate control over RPV water level and level is being returned to the normal band, provide the following cue: Cue: Your task is complete, another operator will complete any remaining actions. FWLC Master Controller is in manual control and RPV Water Level is being restored to the normal band. Page 10 of 12 NRC March 2014 CENG_ a joot ""Me of I 0=:--ion NINE MILE POINT NUCLEAR STATION Evaluator lob Aid Do Not Provide to Candidate Step 5: FEEDWATER BTO FWS-LV10B 2FWS-HIC1010B

-100 :=-eo -:=-eo =-20 -o -The Valve Position Meter and Controller Output Meter must match within S 0 1o of each other prior to resetting the 86 device Controller Output (Horizontal)

Step 10: ::"20 =-.2 JPM S-4 Page 11 of 12 Input Signal (Vertical)

The Controller Output Meter must match within S 0 1o of the Input Signal Meter prior to placing the controller in Automatic Controller Output (Horizontal)

NRC March 2014

a JOint venture NINE MILE POINT NUCLEAR STATION !NJTIAL .. .

CUE JPM S-4 JPM Handout Given:

The plant is at 100% power.

The crew has entered N2-SOP-06, Feedwater Failures due to an LV10B Lockup

The cause of the LV10B Lockup was due to an operator inadvertently bumping a power supply breaker on 2NHS-MCC003

The breaker was inspected for damage and determined to be functioning correctly.

Operators have restored power to LV10B.

The Master FWLC Controller is currently controlling LV10A in automatic with LV10B in manual and locked up at rv35% open

There is no evidence that LV10B is drifting or that Feedwater Pump Limits are being challenged.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions . (Operators Name), Restore LV10B valve control and return LV10B to automatic control per N2-SOP-06, Attachment 1, Step 1.1.3 Page 12 of 12 NRC March 2014 CENG .. NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC Simulator S-5 Revision:

0.0 --=-=-=----

Energize 2ENS*SWG103 from Division 2 EDG and Energize Title: SWG015 (Stub Bus) from 2ENS*SWG103 During a Station Blackout Approvals:

Signature I Printed Name Developed By David Huff 12/18/2013 Validated By Jason Sawyer 12/03/2013 Facility Reviewer Aaron Armstrong , /?eo/'1 Approximate Duration:

__ _::2:...:0_m_in--'u--'t;..;:.e..:...s

__ Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

_________

_ Date: JPM S-5 Page 1 of 12 NRC March 2014 a jOint venture of----, o=-

I NINE MILE POINT NUCLEAR STATION References

1. N2-SOP-03, Loss of AC Power 2. N2-SOP-01 and 02, Station Blackout JPM s-s Page 2 of 12 NRC March 2014 CENG .. a JO"! veotuce ol I NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to Maximize RDS Flow after a reactor scram as well as respond to a high suction strainer differential pressure.

b. This JPM is considered alternate path because once RDS flow is maximized, a high suction strainer differential pressure alarm will occur. The operator will be required to recognize the degraded condition and take conditional steps to mitigate it in accordance with the operating procedure.

2. Task Information:

a. N2-SOP-03-01001, Respond to N2-SOP-03, Loss of AC Power b. K/A 262001, A4.01 (3.4/3.7)

3. Evaluation I Task Criteria Perform Simulator No No Yes 4. Recommended Start Location a. Unit 2 Simulator JPM S-5 Page 3 of 12 NRC March 2014 a JOint venture of*----, 0 =""'""' -;:,eo* J NINE MILE POINT NUCLEAR STATION 5. Simulator Setup (if required)

a. Prepare the simulator as follows: 1) Reset to a Full Power IC 2) Insert the following Malfunctions:

DGOSA EDG1 OVERSPEED DGOSB EDG2 OVERSPEED DG04B EDG3 FAIL TO UV/LOCA AUTO START 3) Insert Malfunctions ED02A and 028 Loss of Line 5 and 6 4) Place the Mode Switch in Shutdown 5) Complete the steps of N2-SOP-03, Attachment 1, Step 1.6 Fault Identification

6) Allow plant conditions to stabilize.

7) Place the Control Switch for the Division 2 EDG to Start 6. JPM Setup (if required)

a. Prepare a copy of N2-SOP-03, and markup section 1.6 as complete.

JPM s-s Provide a copy the Precautions and Limitations, marked up Section 1.6, Section 1.7, Attachment 8, and Attachment

9. Page 4 of 12 NRC March 2014 CENG .. a JOint 'entuce of I NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM S-5 Page 5 of 12 NRC March 2014 a JOJo"entu'e ot I -:,eDF NINE MILE POINT NUCLEAR STATION 1. 2. JPM S-5 Given:

The Reactor has just been manually scrammed.

A Station Blackout (SBO) is in progress.

A loss of coolant condition does NOT exist.

2ENS*SWG 103 & 2NNS-SWG015 are required for SBO recovery.

Division 2 Emergency Diesel Generator is running

Fault identification per N2-SOP-03, Attachment 1, Section 1.6 is complete Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Energize 2ENS*SWG103 from the DIV 2 EDG and 2NNS-SWG015 from 2ENS* SWG103, in accordance with N2-SOP-03, Attachment 1, Section 1. 7. Provide repeat back of initiating cue Cue: Acknowledge repeat back providing correction if necessary.

Obtain a copy of N2-SOP-03 and review I utilize the correct section of the procedure p p SAT I UNSAT STD: Proper communications used lAW CNG-OP-1.01-2001, Communications and Briefings.

SAT I UNSAT STD: Current version of N2-0P-03 obtained and Attachment 1, Step 1.7.5 and Attachment 8 reviewed lAW CNG-PR-2.01-1000, Document Control. The following steps are performed at Panel 852 unless otherwise noted. Page 6 of 12 NRC March 2014 a )O""entuce ot I .. ton NINE MILE POINT NUCLEAR STATION 3. 4. 5. 6. JPM s-s Attachment 8 Prerequisites:

PRIOR to executing the following steps, power must be available from one of the following sources:

Reserve Station Service Transformer 1B (Attachment

6)

Aux Boiler transformer (Attachment

10)

Division II EDG (2EGS*EG3) (N2-0P-100A)

Division III EDG (2EGS*EG2) (N2-0P-100B) Attachment 1, Section 1.6, Fault Identification and Isolation, is complete.

Upon completion of Attachment 8, return to Attachment 1, Section 1.7, as appropriate to restore power to the plant. At switchgear 2ENS*SWG103 (CB 261'), verify reset the following lockouts:

86A-2ENSY02 for Breaker 103-2

86B-2ENSY02 for Breaker 103-2

86A-2ENSY01 for Breaker 103-4

86B-2ENSY01 for Breaker 103-4

86C-2ENSY01 for Breaker 103-N2

86C-2ENSY02 for Breaker 103-N2

86-2EJSY03 for Breaker 103-1

86-2EJSY04 for Breaker 103-13 Cue: As PO, inform the operator that all lockouts listed in Attachment 8 Step 8.1.4 are reset. Page 7 of 12 p p p p SAT I UNSAT STD: Per the turnover provided, determines power is available from the Division 2 EDG. SAT I UNSAT STD: Per the turnover provided, determines Attachment 1, Section 1.6 Fault Identification is Complete.

SAT I UNSAT STD: Determines return to Attachment 1, Section 1.7 is not required at this time. SAT I UNSAT STD: Contacts a PO and directs them to reset lockouts on 2ENS*SWG103 per N2-SOP-03, Attachment 8, Step 8.1.4 NRC March 2014 a JO"t 'eotcce ot I 0 t.J::eoF NINE MILE POINT NUCLEAR STATION PERFORMANCE

7. Attachment 8, Section 8.4: At 2ENS*SWG103 (CB 261') verify reset the following lockouts:

86 2EGPY01 for Breaker 103-13

86-2-2EGPY02 for Breaker 103-14

86-1-2EGPY02 for Breaker 103-14 Cue: As PO, inform the operator that all lockouts listed in Attachment 8 Step 8.4.1 are reset. 8. Place the SYNC switch to ON (SYNCHRONIZE TO BUS 103) 9. Close 103-14 10. Place the SYNC switch to OFF 11. At Panel 601, verify started, one Division II service water pump. ACT. CODE EVALUATOR PIS/ NA p SAT I UNSAT STD: Contacts a PO and directs them to reset lockouts on 2ENS*SWG103 per N2-SOP-03, Attachment 8, Step 8.4.1 p *PASS/ FAIL STD: On 2CEC*PNL852, places the Division 2 EDG SYNCHRONIZE TO BUS 103 switch to ON. p *PASS I FAIL STI): On 2CEC*PNL852, places BREAKER 103-14 control switch to CLOSE p SAT I UNSAT STD: On 2CEC*PNL852, places the Division 2 EDG SYNCHRONIZE TO BUS 103 switch to OFF. p SAT I UNSAT STD: On 2CEC*PNL601, observes GREEN LIGHT off and RED LIGHT on for 2SWP*P1B.

Procedure

caution:

Fluid systems may have drained due to the loss of power. JPM s-s Page 8 of 12 NRC March 2014 a JO'c"entuce of I O=:lllltlon NINE MILE POINT NUCLEAR STATION PERFORMANCE

12. Start additional loads as directed by SMICRS in accordance with Attachment 12 Section 12.1 Cue: As SM, inform the operator that no additional loads need to be started at this time. 13. Return to Attachment 1, Section 1. 7 and then reference Attachment

9. 14. Prerequisites:

PRIOR to executing the following steps, power must be available from one of the following sources:

2NPS-SWG003 (Attachment

7)

2ENS*SWG103 (Division II Emergency Switchgear) (Attachment

8) 15. Attachment 1 Section 1.6 Fault Identification and Isolation is complete.

16. Upon completion of Attachment 9, return to Attachment 1, Section 1. 7, as appropriate to restore power to the plant. JPM 5-5 Page 9 of 12 ACT. CODE EVALUATOR PIS INA p SAT I UNSAT STD: Contacts the SM and determines no additional loads need to be started at this time. p SAT I UNSAT STD: References Attachment 1 Section 1. 7 and determines Attachment 9 is the next section to go to. p SAT I UNSAT STD: Determines power is available from 2ENS*SWG103.

p SAT I UNSAT STD: Per the turnover provided, determines Attachment 1, Section 1.6 Fault Identification is Complete.

p SAT I UNSAT STD: Determines return to Attachment 1, Section 1.7 is not required at this time. NRC March 2014 a JO<e"ectuce ot I 0 =:'lation NINE MILE POINT NUCLEAR STATION PERFORMANCE

17. At Panel 804 (CB 288'), verify reset 86-2NNSY15 (4.16KV BUS NNS-015 PROTECTION LOCKOUT RELAY). Cue: As PO, inform the operator that the lockout listed in Attachment 9 Step 9.1.4 is reset. ACT. CODE EVALUATOR P/5/NA p SAT I UNSAT STD: Contacts a PO and directs them to reset the lockout on Panel 804 per N2-SOP-03, Attachment 9, Step 9.1.4 Pmcedure caution: Energizing 2NNS-SWG015 from 2ENS*SWG103 when the Div II Diesel is supplying the bus is not permitted during a LOCA. 18. Section 9.3: p SAT I UNSAT Place 15-3 in PULL-TO-LOCK.

STD: On 2CEC*PNL852, determines Breaker 15-3 is already in PULL-TO-LOCK. ProcedUre Note: The following step requires a PA 2235 Key located in the CRO's desk. 19. IF 2NNS-SWG015 is needed for SBO p *PASS I FAIL recovery, THEN at Panel 852, place the Div II LOCA SIGNAL BYPASS switch to ON.

turnover that 2NNS-SWG015 is needed for SBO recovery.

Obtains a PA 2235 key from the CRO Desk and at 2CEC*PNL852, places the DIVISION 2 LOCA SIGNAL BYPASS keylock switch to ON. 20. Do NOT exceed the emergency diesel p SAT I UNSAT generator rating, 4400 KW ( 4840 KW 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limit) WHEN re-energizing STUB Bus 2NNS-STD: Observes on the Division 2 EDG Load Meter at SWG015. 2CEC*PNLB52 that the diesel is operating with <4400 KW load. JPM S-5 Page 10 of 12 NRC March 2014 a JOint venture of----, 0=:""' ....

I NINE MILE POINT NUCLEAR STATION PERFORMANCE

21. At 2ENS*SWG103 (CB 261'), verify reset 86-2ENSY12. (Breaker 103-8) Cue: As PO, inform the operator that the lockout listed in Attachment 9 Step 9.3.4 is reset. 22. Close 103-8 23. Close 15-8. ACT. CODE PI 5 INA p p p EVALUATOR SAT I UNSAT STD: Contacts a PO and directs them to reset the lockout on 2ENS*SWG103 per N2-SOP-03, Attachment 9, Step 9.3.4 *PASS I FAIL STD: On 2CEC*PNL852, places BREAKER 103-8 control switch to CLOSE *PASS I FAIL STD: On 2CEC*PNL852, places BREAKER 15-8 control switch to CLOSE TERMINAnNG CUE 2ENS*SWG103 is being powered from the Division 2 EDG and SWG015 is being powered from 2ENS*SWG103.

I STOPTIME JPM s-s Page 11 of 12 NRC March 2014 a JOtnt venture of---, 0=--;:,eo* I NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INITIATING CUE JPM S-5 JPM Handout Given:

The Reactor has just been manually scrammed.

A Station Blackout (SBO) is in progress.

A loss of coolant condition does NOT exist.

2ENS*SWG 103 & 2NNS-SWG015 are required for SBO recovery.

Division 2 Emergency Diesel Generator is running

Fault identification per N2-SOP-03, Attachment 1, Section 1.6 is complete Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Energize 2ENS*SWG103 from the DIV 2 EDG and 2NNS-SWG015 from 2ENS* SWG103/ in accordance with N2-SOP-03/

Attachment 1/ Section 1. 7. Page 12 of 12 NRC March 2014 CENG ... NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC Simulator S-6 Revision:

0.0 ---=...:....=....

__ _ Title: Bypass RCIC Room High Temperature Isolation (Alternate Path) Approvals:

Signature I Printed Name Developed By David Huff 12/18/2013 Validated By Jason Sawyer 12/03/2013 Facility Reviewer Aaron Armstrong , ,13 j?...oJ Approximate Duration:

___ 1_;;5_m_in_u:...._ct;....:..e..:...s

__ Documentation of Performance:

Performer:

Evaluator:.

Start Time: ----Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

_________

_ Date: JPM S-6 Page 1 of 11 NRC March 2014 a JO<e"entuce of I -;,',eoF NINE MILE POINT NUCLEAR STATION References

1. N2-SOP-02, Station Blackout Support Procedure JPM S-6 Page 2 of 11 NRC March 2014

a JOint venture of o=:*lon ..:,eDF I NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability bypass the RCIC Room High Temperature Isolations during a Station Blackout as well as reset a RCIC Turbine Trip from the Control Room. b. This JPM is considered alternate path because once the RCIC Room High Temperature Isolations have been bypassed, a RCIC Turbine Trip will occur. The operator will mitigate by resetting the RCIC turbine from the Control Room. 2. Task Information:

a. N2-21700-01048, Latch the RCIC TTV From The Control Room b. K/A 217000, A4.02 (3.9/3.9)

3. Evaluation I Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical Task No Alternate Path Yes LOD >1.0 Yes 4. Recommended Start Location a. Unit 2 Simulator JPM S-6 Page 3 of 11 NRC March 2014 CENG., a )O<et 'entuce of I

-:,*::eoF NINE MILE POINT NUCLEAR STATION 5. Simulator Setup (if required)

a. Prepare the simulator as follows: 1) Reset to a full power IC 2) Place the Mode Switch in Shutdown and manually trip the turbine 3) Insert Malfunctions ED02A and ED02B, Loss of Lines 5 and 6. 4) Manually initiate RCIC 5) Insert Remote Function RC02A, RCIC Level 8 Defeated, FV=DEFEATED

6) Manually Initiate Division 1 and 2 ECCS Systems 7) Insert Malfunctions EDOSA, EDOSB, and EDOSC to deenergize Division 1, 2, and 3 emergency busses. 8) Insert Malfunction RR20, DBA LOCA at a value of 0.2°/o 9) Insert Override AN601332, RCIC TEMPERATURE HIGH to ON b. Set Malfunction RC06, RCIC TURBINE TRIP FV=TRUE on Trigger 1 with a no time delay c. Set the following Event Trigger on Event 1: Event Action: ZDLDS4B(1)==1 Command: Blank

Description:

Keylock Switch E31-S4B in BYPASS. d. Set the following Event Trigger on Event 2: Event Action: HZLRCV150(2)==0 Command: DMF RC06

Description:

MOV150 Red Light Off. JPM S-6 Page 4 of 11 NRC March 2014 a jOint venture ol--0 =""""' -J,eoF I NINE MILE POINT NUCLEAR STATION 6. JPM Setup (if required)

a. Prepare a copy of N2-SOP-02, Attachment

4. No steps need to be marked up. JPM S-6 Page 5 of 11 NRC March 2014 a JOir>t venture of I NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM S-6 Page 6 of 11 NRC March 2014 a JOifll venture of 1 ..:::eoF NINE MILE POINT NUCLEAR STATION Given: INlnAL CONDITIONS

The plant has experienced a Station Blackout.

N2-SOP-2, Station Blackout Support Procedure, is in progress.

Drywell pressure is above 1.68 psig due to a LOCA

RCIC is in service, injecting into the core. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions INITIATING CUE (Operators Name),) Bypass the RCIC Room High Temperature Isolations in accordance with N2-50P-02, Attachment

4. START TIME 1. 2. PERFORMANCE Provide repeat back of initiating cue Cue: Acknowledge repeat back providing correction if necessary.

Obtain a copy of N2-SOP-02 and review I utilize the correct section of the procedure, Determines that Attachment 4, Step 3.1 is not applicable at this time. ACT. CODE PIS INA p p EVALUATOR SAT I UNSAT STD: Proper communications used JAW CNG-OP-1.01-2001, Communications and Briefings.

SAT I UNSAT STD: Current version of N2-SOP-02 obtained and Attachment 4 reviewed JAW CNG-PR-2.01-1000, Document Control. The following annunciators will alarm during performance of the next step: ProCedure Note:

601306, Division I RWCUIRCICIRHR ISOLATION IN BYPASS 3. JPM S-6

601307, DIVISION II RWCUIRCIC/RHR ISOLATION IN BYPASS Places the following switches in BYPASS

E31A-S2A, STEAM SUPPLY LINE OUTBD !SOL. VLV. BYPASS ICS*MOV121 Page 7 of 11 p *PASS I FAIL STD: Obtains a key from the CRO desk and at 2CEC*PNL632, places keylock switch E3tA-S2A to BYPASS. NRC March 2014 CENG .. a JO<et '""'"e ol I 0 NINE MILE POINT NUCLEAR STATION PERFORMANC.E

4.

E31A-S4A, RHR/RCIC ISOLATION BYPASS 5.

31A-S2B, STEAM SUPPLY LINE INBD ISOL. VLV. BYPASS ICS*MOV128 ACT. CODE PIS/ NA p p EVALUATOR

PASS/ FAIL STD: Obtains a key from the CRO desk and at 2CEC*PNL632,pfaceskeyrock switch E3J.A.o.S4Ato BYPASS. *PASS/ FAIL STD:. Obtains a key from the CRO desk and at 2CEC*PNL642, places key/ock switch E31A.:.S2B to BYPASS. Alt$'nate Path: Completion of the next step will cause the RCIC Turbine to trip. The operator will mitigate the event by resetting the RCIC TTV from the Control Room 6. 7.

E31A-S4B, RHR/RCIC ISOLATION BYPASS Cue: If the operator does not respond to the RCIC turbine trip, provide a prompt to have them evaluate conditions on 2CEC*PNL601.

Identify and report RCIC Turbine Has Tripped Cue: As CRS, acknowledge report. Inform the operator that the cause of the trip is known and corrected.

Direct the operator to reset and reopen 2ICS*MOV150 from the control room. p p *PASS/ FAIL STD: Obtains a key from the CRO desk ancl at switch E31A-:-S4B to BYPASS. SAT I UNSAT STD: Identifies that Annunciators 601301 and 601305 are in alarm. Observes the 2ICS*MOV150 is closed. Informs the CRS. .. . . . . . *. Prc:tCedure Note: The following annunciators will alarm during performance of the next step:

852136 EDG 1 LOCA Bypass Switch ON JPM S-6 Page 8 of 11 NRC March 2014 CENG .. a JO"' veotuce of I O=:'""kwl NINE MILE POINT NUCLEAR STATION 8. 9. PERFORMANCE References N2-SOP-02, Attachment 4, Step 3.1: IF the RCIC turbine trip throttle valve (2ICS*MOV150) trips with a LOCA signal present, THEN perform the following:

Place in ON the Division I LOCA SIGNAL BYPASS switch at P852

Reset 2ICS*MOV150 at P601 ACT. CODE P/S/NA p p EVALUATOR

PASS I FAIL STD: Determines a LOCA signal is present per the initial conditions.

Obtains a key from the CRO desk and at 2CEC*PNL851, places the DNISION 1 EDG LOCA SIGNAL BYPASS keylock switch to BYPASS *PASS/ FAIL STD: At 2CEC*PNL601, Places the Control Switch for ICS*MOVJ.SO.to CLOSE and doses the as indicated by the GREEN light lit and RED light not lit. Procedure

Note: The following annunciator will clear during performance of the next step:

852136 EDG 1 LOCA Bypass Switch ON 10.

At Panel 2CEC*PNL852, verify LOCA p SAT I UNSAT JPM S-6 SIGNAL BYPASS switch in OFF for 2EGS*EG1 Division I Diesel Generator STD: At 2CEC*PNL851, places the DIVISION 1 EDG LOCA SIGNAL BYPASS keylock switch to OFF The reopening of 2ICS*MOV150 may be done prior to placing the LOCA SIGNAL BYPASS switch to OFF. Additionally, the operator may choose to reference N2-EOP-HC and/or N2-0P-35 for guidance on reopening 2ICS*MOV150.

The critical step is to reopen 2ICS*MOV150 from CEC*PNL601.

Which procedure (or no procedure) they use to accomplish this is not important to the grading of the step. Page 9 of 11 NRC March 2014 a JO'""entuce ot I NINE MILE POINT NUCLEAR STATION ',** PERFORMANCE ACT. CODE EVALUATOR PI 5 INA 11. Open 2ICS*MOV150 p *PASS/ FAIL Evaluator Note: TE.RMINAnNG CUE STOP TIME JPM S-6 STD: At 2CEC*PNL6Cl, Places the Control Switch for ICS*MOV1.50 to OPEN and opens the valve as indicated by the GREEN light not lit and RED light lit. The operator may choose to slowly open MOVJ..SO using intermittent operation of the control switch. This is also acceptable.

Once 2ICS*MOV150 has been opened, provide the following cue: Cue: Your task is complete, another operator will complete any remaining actions. The RCIC Room High Temperature Isolations are bypassed and 2ICS*MOV150 has been reset and reopened.

Page 10 of 11 NRC March 2014 a J01'1t venture of I NINE MILE POINT NUCLEAR STATION INITIAL CONDittONS INITIATING CUE JPM S-6 JPM Handout Given:

The plant has experienced a Station Blackout.

N2-SOP-2, Station Blackout Support Procedure, is in progress.

Drywell pressure is above 1.68 psig due to a LOCA

RCIC is in service, injecting into the core. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name),) Bypass the RCIC Room High Temperature Isolations in accordance with N2-SOP-02, Attachment

4. Page 11 of 11 NRC March 2014 CENG NINE MILE PGlhiT NUCLEAR s*1i\TION Training Id: 2013 NRC Simulator S-7 Revision:

1.0 --=-=-=-----

Override the Control Room Envelope ACU Cross-Divisional Title: Operating Interlock (Time Critical)

Approvals:

Signature I Printed Name Developed By _

02/14/2014 Validated By Jason Sawyer 12/03/2013 Facility Reviewer Aaron Armstrong z./\8j:J.JJ 1'1 Approximate Duration : ----=1=3--m_i n--=u--=tc.c::..e-'--s

__ Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

Date: JPM S-7 Page 1 of 12 NRC March 2014 NINE MILE POINT NUCLEAR STATION References

1. N2-0P-53A, Control Building Ventilation System JPM S-7 Page 2 of 12 NRC March 2014 CENG. <l.JOI'lt venture oi J 0 =:'laHon NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to override the Control Room Envelope ACU Cross-Divisional Operating Interlock.

b. The critical tasks of this JPM must be completed within 13 minutes of starting the JPM. Failure to complete the steps may cause the control room temperature to rise above 90°F. 2. Task Information:

a. N2-288003-01051, Perform Override of Control Room Envelope ACU Cross-Divisional Operations Interlock

b. K/A 290003 A3.01 3.3/3.5 3. Evaluation 1 Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical Task Yes Alternate Path No LOD >1.0 Yes 4. Recommended Start Location a. Unit 2 Simulator

5. Simulator Setup (if required)

a. Prepare the simulator as follows: JPM S-7 Page 3 of 12 NRC March 2014 CENGW NINE MILE POINT NUCLEAR STATION 1) Reset to full power IC 2) Place the control switches for ACU1A and 2A to PULL TO LOCK. Observe that ACU1B and 2B have auto started. The interlocks have a time delay so it may take a few seconds. 3) Place the control switches for ACU1A and 2A back to RED FLAG. ACU1A and 2A should not restart due to interlock.

The point is to make it look like ACU1A and 2A tripped and 1B and 2B auto started. 4) Insert Overrides for AN870326 and AN870327, CONTROL ROOM C UNIT 1A AUTO TRIP and RELAY ROOM AC UNIT 2A AUTO TRIP, FV=CRYWOLF

5) Insert Override AN849128, FIRE DETECTED PNL 129 W STAIR/288, FV=CRY WOLF 6. JPM Setup (if required)

a. Prepare a copy of N2-0P-53A, Section 15.0. Include a copy of the precautions and limitations.

JPM S-7 Page 4 of 12 NRC March 2014 CENGN a]OI'1tventureof--J 0 =:'latton NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM S-7 Page 5 of 12 NRC March 2014 CENG .. <I JOint venture oi __ J et,eDF NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INITIATING CUE START TIME Given:

The reactor is at 100% power.

A fire has occurred in the Control Building

Annunciator 849128, FIRE DETECTED PNL 129 W STAIRI288 is in alarm, with Fire Zone 352 NW as the affected zone.

The Fire Brigade Leader has confirmed the fire

2HVC*ACU1A and 2A were running and have since tripped due to the fire.

2HVC*ACU1B and 2HVC*ACU2B have auto started.

The Shift Manager's permission has been received to override the control room envelope ACU cross-divisional operating interlock.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Override the Control Room Envelope ACU Divisional Operating Interlock per N2-0P-53A, Section H.15.0. This is a Time Critical JPM PERFORMANCE ACT. CODE EVALUATOR PIS INA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used lAW CNG-OP-1.01-2001, Communications and Briefings.

2. Obtain a copy of N2-0P-53A and review I p SAT I UNSAT utilize the correct section of the procedure STD: Current version of N2-0P-53A obtained and Step H.15.0 reviewed lAW CNG-PR-2.01-1000, Document Control. Procedure

The control logic for the Control Room Envelope air handling units JPM S-7 Page 6 of 12 NRC March 2014 CENG a ]Oint venture of--] 0 =:llatlon NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE P/S/NA EVALUATOR Note: 2HVC*ACU1AIB and *ACU2AIB includes a start permissive which precludes simultaneous operation the units and is intended to auto start the unit in the opposite division in the event of a trip of the running unit. A fire affecting one division has the potential to override this interlock such that the opposite division ACU may become disabled.

This subsection will utilize override switches to ensure operability of the division without the fire. 3. 4. JPM 5-7

Actuation of the override switches is required to be completed within 13 minutes after a fire that has disabled the previously running Control Room Envelope ACUs to ensure Control Room Envelope temperature remains <90°F.

This section is only used in response to a confirmed fire in Fire Areas 16, 17, 18 or 19.

The actions in this section are performed at 2CEC*PNL870(871) unless otherwise specified.

The Fire Zones listed in Step H.15.1 affect Division I components.

IF the fire is in any of the following Fire Zones:

321NW-Cable Chase West, Control Bldg, 237' (Fire Area 16)

332NW -Cable Chase West, Control Bldg, 261' (Fire Area 16)

352NW -Cable Chase West, Control Bldg, 288'6" (Fire Area 16)

371NW-Cable Chase West, Control Bldg, 306' (Fire Area 16)

333XL -Div I Switchgear Room, Control Bldg, 261' (Fire Area 17) THEN perform the following:

Check the following ACUs are available OR are in service:

HVC*ACU1B, CONTROL ROOM AC FAN

HVC*ACU2B, RELAY ROOM AC FAN Page 7 of 12 p p SAT I UNSAT STD: Determines per the turnover that the fire is in Fire Zone 352 NW (Fire Area 16). Determines that the Division 1 ACUs are affected and that the Cross-Divisional interlocks need to be disabled for Division 2 components.

Continues on in Section H.15.1. SAT I UNSAT STD: Observes the RED running lights for ACU1B and 28 are lit and that the GREEN not-running lights are not lit. NRC March 2014 CENG." 8JOI'ltventuceof--J NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE EVALUATOR PIS INA Procedure The following steps will cause an auto start of HVC*ACUlB and *ACU2B, if not Note: already running. 5. Verify control switch is in PULL-TO-LOCK for p *PASS I FAIL the following:

HVC*ACUlA, CONTROL ROOM AC FAN STD: At 2CEC*PNL870, places the control switch for HVC*ACUlA in Pull-To-Lock. 6.

HVC*ACU2A, RELAY ROOM AC FAN p *PASS I FAIL STD: At 2CEC*PNL870, places the control switch for HVC*ACU2A in Pull-To-Lock. 7. Notify SM to declare 2HVC*ACU1A AND p SAT I UNSAT 2HVC*ACU2A inoperable AND to take actions per TS 3.7.2 AND 3.7.3. STD: Contact the SM and informs him that HVC* lA and Cue: As SM, inform the operator that ACU1A 2A are inoperable.

and 2A have been declared inoperable and TS 3.7.2 and 3.7.3 have been reviewed.

8. Obtain SM permission to override the HVC p SAT I UNSAT ACU cross divisional operating interlock for 2HVC*ACU1A AND 2HVC*ACU2A STD: Refers to the initial conditions and determines that Cue: If necessary, as the SM, inform the the SM has been given operator that he has permission to permission to override the override the cross divisional interlock cross divisional interlocks for for ACU1A and 2A. ACUlA and 2A. Procedure If HVC*ACUlB is not running, the following step should cause an automatic start Note: of HVC*ACUlB.

JPM S-7 Page 8 of 12 NRC March 2014 CENG ... NINE MILE POINT NUCLEAR STATION PERFORMANCE

9. At 2CEC*PNL871, place keylock switch APPENDIX R CR ACU1B OVERRIDE SW, to OVERRIDE.

Cue: If necessary, inform the operator that another operator will perform the independent verification and to continue on with the procedure.

10. Verify HVC*ACU1B running. 11. WHILE continuing in this subsection, wait approximately 2 minutes, THEN confirm proper operation of HVC*ACU1B.

12. Place HVC*ACU1B control switch, CONTROL ROOM AC FAN, in Normal-After-START.

ACT. CODE PIS INA p p p p EVALUATOR

PASS I FAIL STD: Obtains a key from the CRO desk and at 2CEC*PNL871, places the APPENDIX R CR ACU1B OVERRIDE KEYLOCK SW to OVERRIDE.

SAT I UNSAT STD: Observes the RED running light is lit and the GREEN off light is not lit for ACU1B SAT I UNSAT STD: Determines the time the Appendix R switch was placed in OVERRIDE and determines when two minutes will be completed.

Continues on to the next step while waiting for two minutes to be complete.

SAT I UNSAT STD: At 2CEC*PNL871, places the control switch for HVC*ACU18 in NORMAL-AFTER-START (i.e. Red Flag). Procedure If HVC*ACU2B is not running, the following step should cause an automatic start Note: of HVC*ACU2B.

13. At 2CEC*PNL871, place keylock switch p *PASS I FAIL APPENDIX R RR ACU2B OVERRIDE SW, to OVERRIDE.

STD: Obtains a key from the CRO desk and at 2CEC*PNL871, places the APPENDIX R CR ACU2B OVERRIDE KEYLOCK SW to OVERRIDE.

JPM S-7 Page 9 of 12 NRC March 2014 CENG., a JOI"t venture of J

-1,eDF NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE PIS INA EVALUATOR Once the second Appendix R switch is placed in OVERRIDE, mark down the time the step was completed here: Evaluators Note: Calculate the time the operator took to complete the critical steps of the JPM by subtracting the start time from the time documented above. Document the 14. completed time here: _____ minutes Evaluator, determine if the critical task completion time was within the required timeframe.

15. Verify HVC*ACU2B running. 16. WHILE continuing in this subsection, wait approximately 2 minutes, THEN confirm proper operation of HVC*ACU2B.

17. Place HVC*ACU2B control switch, RELAY ROOM AC FAN, in Normal-After-START.

NIA p p p *PASS I FAIL STD: All operator critical steps of this JPM completed within 13 minutes from the start of the JPM. SAT I UNSAT STD: Observes the RED running light is lit and the GREEN off light is not fit for ACU2B SAT I UNSAT STD: Determines the time the Appendix R switch was placed in OVERRIDE and determines when two minutes will be completed.

Continues on to the next step while waiting for two minutes to be complete.

SAT I UNSAT STD: At 2CEC*PNL871, places the control switch for HVC*ACU2B in AFTER-START (i.e. Red Flag). Evaluators Note: Once the HVC*ACU2B control switch is placed in NORMAL-AFTER-START, provide the following cue: JPM S-7 Cue: Your task is complete.

Another operator will complete any remaining actions. Page 10 of 12 NRC March 2014 CENG .. a J01'1t venture of--] O=:u.tlon NINE MILE POINT NUCLEAR S fATION TERMINATING CUE STOP TIME JPM S-7 The two appendix R switches for ACU1B and 28 have been placed in OVERRIDE.

Page 11 of 12 NRC March 2014 CENG .. ClJOintventure o'--J O=:u.tion NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INITIATING CUE JPM S-7 JPM Handout Given:

The reactor is at 100% power.

A fire has occurred in the Control Building

Annunciator 849128, FIRE DETECTED PNL 129 W STAIR/288 is in alarm, with Fire Zone 352 NW as the affected zone.

The Fire Brigade Leader has confirmed the fire

2HVC*ACU1A and 2A were running and have since tripped due to the fire.

2HVC*ACU1B and 2HVC*ACU2B have auto started.

The Shift Manager's permission has been received to override the control room envelope ACU cross-divisional operating interlock.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Override the Control Room Envelope ACU Divisional Operating Interlock per N2-0P-53A, Section H.15.0. This is a Time Critical JPM Page 12 of 12 NRC March 2014 CENG_.

NINE MILE POINT NUCLEAR STA110N Training Id: 2013 NRC Simulator S-8 Revision:

--=.0.:..:.0:::....__

__ Title: Respond to an Inadvertent Closure of 2SWP*MOVSOB Approvals:

Signature I Printed Name Developed.

By David Huff 12/18/2013 Validated By Jason Sawyer 12/03/2013 Facility Reviewer ' Aaron Armstrong 1 J $ /z.o l'f I I Approximate Duration : __ ....::2:....:0'---m'--'---i n'-u'-t'-e.;:_s

__ Documentation of Performance:

Performer:

Evaluator:*

Start Time: ----Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

Date: JPM S-8 Page 1 of 14 NRC March 2014 CENG,. a JOint venture of---, 0=""""" -:;,eoF I NINE MILE POINT NUCLEAR STATION References

1. N2-SOP-11, Loss or Degraded SWP System JPM S-8 Page 2 of 14 NRC March 2014 a JO'c"ecJuce of I -!,eDF NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to respond to an inadvertent closure of 2SWP*MOVSOB per N2-SOP-11

2. Task Information:

a. N2-SOP-11-01001, Respond to SOP-11, Loss of or Degraded Service Water System b. K/A 400000, A4.01 (3.1/3.0)

3. Evaluation I Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical Task No Alternate Path No LOO >1.0 Yes 4. Recommended Start Location a. Unit 2 Simulator

5. Simulator Setup (if required)

a. Prepare the simulator as follows: 1) Reset to full power IC 2) Place the control switches for 2SWP*MOVSOB in the CLOSE position and allow it to fully shut. JPM S-8 Page 3 of 14 NRC March 2014 a JOint venture of---, o=--::,eDF I NINE MILE POINT NUCLEAR STATION 3) Allow plant conditions to stabilize for a few minutes. 6. JPM Setup (if required)

a. Prepare a copy of N2-SOP-ll.

Include a copy of the Discussion section as well as Attachment

1. JPM S-8 Page 4 of 14 NRC March 2014 a JO"I veotuce ol I NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM S-8 Page 5 of 14 NRC March 2014 a JOint venture of---, O=""'lon -J,eDF I NINE MILE POINT NUCLEAR STATION INITIAL CON.DITIONS .I"ITIA1l:NG cue START TIME Given:

The plant is at 100% power

An inadvertent closure of 2SWP*MOVSOB, PMP 1B DISCH HEADER CROSS-TIE ISOL VLV occurred.

NO Operator Actions have been completed.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Enter N2-SOP-11, Loss or Degraded Service Water and perform all applicable actions for an inadvertent closure of 2SWP*MOV508.

PERFORMANCE ACT. CODE EVALUATOR PIS/ NA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used lAW CNG-OP-1.01-2001, Communications and Briefings.

2. Obtain a copy of N2-SOP-11 and review I p SAT I UNSAT utilize the correct section of the procedure STD: Current version of N2-0P-11 obtained and the flowchart and Attachment 11 reviewed lAW CNG-PR-2.01-1000, Document Control. Writes the Date and Time the SOP was entered on the top of the flowchart . .. *

' *" Steps 3 through 6 may be performed in any order and/or may be delayed until Note:** the "THEN" statement of the override is ready to be performed.

JPM S-8 Page 6 of 14 NRC March 2014 CENG .. a]Ointventureof*

__ _ o=Hatlon I NINE MILE POINT NUCLEAR STATION PERFORMANCE

3. Reviews the overrides of N2-SOP-11 and determines the following overrides are met:

SWP pump flow is GREATER THAN 10,000 gpm 4.

Additional SWP flow is required 5.

Pump flow can NOT be maintained above low flow alarm, 6.

2SWP*MOVSOA(B) is inadvertently closed AND SWP non-essential header isolation valves are NOT closed. Cue: If asked, inform the operator that MOVSOB was inadvertently shut due to operator error. JPM S-8 Page 7 of 14 ACT. CODE EVALUATOR PIS INA p SAT I UNSAT STD: On 2CEC*PNL601, observes that the Division 1 SWP flow indicators 2SWP*FI96A and C indicate SWP P1A and C flows are >10K gpm. p SAT I UNSAT STD: On 2CEC*PNL601, observes that the Division 1 SWP flow indicators 2SWP*FI96A and C indicate SWP P1A and C flows are >10K gpm and that additional SWP flow could be necessary at this time. p SAT I UNSAT STD: On 2CEC*PNL601, observes that Annunciator 601219 is in alarm and that 2SWP*FI96B and D indicate low flow. p SAT I UNSAT STD: Determines per the turnover that 2SWP*MOVSOB inadvertently closed. Additionally, on 2CEC*PNL601, observes the RED OPEN light lit and the GREEN CLOSED light not lit for 2SWP*MOVSOB.

NRC March 2014

a JOint venture of I NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE P/5/NA EVALUATOR Evaluators Note: There are several strategies for successful mitigation of this event prior to executing Attachment

1. The expected course of action would be for the operator to first start SWP P1E and then throttle the MOV74's of the Division 1 pumps to maintain flows ::510K gpm. The low flow alarm on Division 2 would then be mitigated by establishing SWP flow through RHS B Heat Exchanger.

Alternatively, the operator may choose to not start an extra Division 1 pump at this time and instead choose to only throttle the MOV74s on the already running Division 1 pumps. Either of these methods is acceptable.

If the operator chooses not to start another pump at this time, then that step may marked as N/A and is not required to be graded. Evaluators Steps 7, 8, and 9 may be performed in any order. Step 11 (Attachment

1) Note: however should not be performed without first completing Steps 8 and 9 . .. While executing the following step, the operator may choose to reference N2-0P-Evaluators 11 for starting of the additional service water pump. Additionally, the operator Note: may choose to use the general guidance of N2-SOP-11 for starting of the pump. 7. Either method is acceptable.

Start additional SWP pumps. Cue: As appropriate, if contacted as a PO, provide feedback to the operator that prestart checks/venting of strainers/good start checks/etc.

have been completed.

p *PASS I FAIL I NA STD: At 2CEC*PNL601, Places the Control Switch for 2SWP*P1E in START. Observes that amps and flow rise on the P1E meters. :Evaluators Note.: Successful completion of Step 8 may require the operator to alternate throttling of MOV74's to maintain both pump flows below 10K gpm as indicated on 2SWP*FI96A, C, and/or E. This is acceptable and the step should be graded as PASS provided that at the completion of the step, all pump flows are ::510K gpm. 8. JPM S-8 Throttle SWP*MOV74s as required to maintain pump flow LESS THAN 10,000 gpm. Page 8 of 14 p *PASS I FAIL STD: On 2CEC*PNL601, throttles the 2SWP*MOV74A, C, andjor E CONTROL SWITCHES as necessary to achieve S10K gpm on 2SWP*FI96A, C, and E. NRC March 2014 CENG .. a pot 'entuce ot I -;:,eDF NINE MILE POINT NUCLEAR STATION 9. 10. PERFORMANCE Throttle SWP flow through an RHR HX as required.

Cue: If asked as RP, inform the operator that RE23B has been placed in service. Attachment 1:

ACT. CODE PIS INA p p EVALUATOR

PASS I FAJ:L STD: On 2CEC*PNL601, places the CONTROL SWITCH for 2SWP*MOV90B to OPEN. Observes .the RE[) OPEN light lit and the. GREEN CLOSED light not lit. *PASS/ PAlL STD: On 2CEC*PNL601, the CONTROL SWITCH for SWP*MOV338 to OPEN and throttles service water flow as necessary to cause Annunciator 601219 to dear. Service water flow to RHS B HX on E12-R602B should not go above 7400gpm. Procedure 1 Note: Initial actions to stabilize the Service Water System are taken per the flowchart and should result in three Division I Service Water Pumps running (if available) with their associated Discharge MOVs throttled as required to maintain pump flows at 10,000 gpm and Service Water flow established to RHS "B" Heat Exchanger to maintain flow for the running Division II Pumps above 2,500 gpm. 11. JPM S-8

This Attachment is written for actions to re-open the closed Service Water Cross-Tie MOVs to meet the one hour action in Tech Spec 3.7.1, Action A.l. Perform Attachment 1: Dispatch Operators to the Valves AND Breakers to determine whether SWP Tie MOV(s) may be re-opened Cue: As the PO dispatched to perform an inspection of the valve and breaker, inform the operator that the inspection was completed and there are no issues with the valve or breaker. Page 9 of 14 p SAT I UNSAT STD: Contacts a PO and dispatches them to 2SWP*MOV50B and its associated breaker and directs them to inspect them for abnormalities.

NRC March 2014 CENG .. a JOint 'entun> of I O=:natlon NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE PIS/ NA EVALUATOR "Evaluators

'. : ...

For grading of the below step, the operator may choose either 2SWP*P1B or D to secure. Either one is acceptable.

For the pump that is not secured, grading of the applicable step is not required and the step may be marked as N/A. 12. 13. 14. JPM S-8 WHEN it has been determined that Service Water System conditions allow re-opening the SWP Cross-Tie MOV(s), reduce the number of operating Division II Service Water Pumps to one by placing control switches in Normal-After-STOP AND verifying that the associated Discharge MOVs close: Cue: If asked as the CRS, inform the operator you have no preference for which pump to secure.

2SWP*P1B AND 2SWP*MOV74B

2SWP*P1D AND 2SWP*MOV74D

2SWP*P1F AND 2SWP*MOV74F Page 10 of 14 p p p *PASS l FAIL l NA STD: At 2CEC*f'NL60l, places the Control Switch for 2SWP*Pl8 in STOP. Obseives that MOV748 fully closes as indicated by the RED OPEN light not lit ahd the GREEN CLOSED light lit. *PASS l FAIL I NA STD: At 2CEC*PNL601 1 places the Control Switch for 2SWP*PlD in STOP; Obseives that MOV748 fully closes as indicated by the RED OPEN light not lit and the GREEN CLO$ED light lit. SAT I UNSAT STD: At 2CEC*PNL601, determines 2SWP*P1E is already secured. Marks this step as NA NRC March 2014 CENG,. a JOint venture of---

NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE PIS INA EVALUATOR

15. IF 2SWP*MOVSOA was closed, open 2SWP*MOVSOA by taking BOTH control switches to OPEN p SAT/ UNSAT STD: At 2CEC*PNL601, determines that 2SWP*MOV50A is NOT closed by observing the RED OPEN light lit and the GREEN CLOSED light not lit. Marks this step as NA 16. IF 2SWP*MOVSOB was closed, open 2SWP*MOVSOB by taking BOTH control switches to OPEN p *PASS I FAIL STD: Places BOTH the CONTROL SWITCHES for 2SWP*MOVSOB one at a time to the OPEN position.

Observes the.RED OPEN light is lit and the GREEN CLOSED UGHT is not lit. Procedure The following two steps may be performed concurrently.

Note: Evaluators Steps 17, 18, and 19 may be performed in any order. Note: Evalu.ators

,'c0' v .Note: JPM S-8 If the operator chose to not start an additional pump while performing the initial flow chart actions, then in order to successfully complete the step for reopening the MOV74's in Division 1, they must start one additional service water pump. If 4 service water pumps are all ready running, then Step 17 may be marked as N/A and is not required to be graded. If however only 3 service water pumps are running at this time, then the operator is required to start an additional service water pump and Step 17 is required to be graded. For Step 17, the operator may choose to start/restart any additional SWP pump from Division 1 or 2. Additionally, the operator may choose to reference N2-0P-11 or N2-SOP-11 for starting of the additional service water pump. Either method is acceptable.

Step 17 may be performed at anytime while in Attachment

1. Page 11 of 14 NRC March 2014 a IO""entuce ot I

-::,eoF NINE MILE POINT NUCLEAR STATION PERFORMANCE

17. Start an additional Service Water Pump Cue: If asked as the CRS, inform the operator you have no preference for which pump to start. Cue: As appropriate, if contacted as a PO, provide feedback to the operator that prestart checks/venting of strainers/good start checks/etc.

have been completed.

18. WHILE maintaining a minimum of 2,500 gpm on the running Division II Service Water Pumps, slowly close 2SWP*MOV33B ACT. CODE EVALUATOR P/5/NA p *PASS l FAIL I NA STD: At 2CEC*PNL601, Places the Control Switch for 2SWP*P18, D, E, or Fin NORMAL-AFTER-START.

Observes that amps and flow rise .on the selected pump meters. p *PASS I FAIL STD: On 2CEC*PNL601, places the CONTROL SWITCH for 2SWP*MOV33B to Observes the RED OPEN light not lit and the GREEN CLOSED light lit:. If the operator has not started a 4th service water pump before attempting to Evaluators complete the next step, they will be unable to fully open all Division 1 MOV74's. Note: If necessary, provide the following cue if this situation occurs: Cue: Start a fourth service water pump per the initial flow chart override of N2-SOP-11. 19. WHILE maintaining Pump flows less than p *PASS/ FAIL 10,000 gpm, slowly open Discharge MOVs for the running Division I Service Water Pumps STD: On 2CEC*PNL601, throttles the 2SWP*MOV74A, C, and/ of E CONTROL SWITCHES as necessary to achieve .all MOV74's open as indicated by their RED OPEN lights lit and their GREEN CLOSED lights not lit. JPM S-8 Page 12 of 14 NRC March 2014 a pnt 'entuce ot I NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE EVALUATOR P/5/NA 20. Close 2SWP*MOV90B p SAT I UNSAT Evaluators Note: *TERMINATING CUE I STOPTIME JPM S-8 STD: On 2CEC*PNL601, places the CONTROL SWITCH for 2SWP*MOV90B to CLOSE. Observes the RED OPEN light not lit and the GREEN CLOSED light lit. Once the operator has placed the control switch for 2SWP*MOV90B in the CLOSE position, then provide the following cue: Cue: Your task is complete.

Another operator will complete any remaining actions. 2SWP*MOV50B is open, flow is secured through RHS B Heat Exchanger, all MOV74's are fully open with all pump flows gpm. Page 13 of 14 NRC March 2014 e JO"t ventuce of I NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS . INITIATING CUE JPM S-8 JPM Handout Given:

The plant is at 100% power

An inadvertent closure of 2SWP*MOVSOB, PMP 18 DISCH HEADER CROSS-TIE ISOL VLV occurred.

NO Operator Actions have been completed.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Enter N2-SOP-11, Loss or Degraded Service Water and perform all applicable actions for an inadvertent closure of 2SWP*MOV508.

Page 14 of 14 NRC March 2014 CENG. NINE MIL.E POINT NUCL£AR STATION Training Id: 2013 NRC Plant P-1A Revision:

2.0 ___;:;____;_

__ _ Title: Local Start of Division 1 Diesel Generator (Alternate Path) Approvals:

Signature I Printed Name Developed By _4------David Huff 02/11/2014 Validated By Mike Storms 12/13/2013 Facility Reviewer Aaron Armstrong /w} 1 Approximate Duration:

20 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

Date: JPM P-lA Page 1 of 16 NRC March 2014 CENG .. a )01'11 venture of J NINE MILE POINT NUCLEAR STATION References

1. NS-OSP-EGS-M@OOl, Diesel Generator and Diesel Air Start Valve Operability Test -Division 1 and 2 2. N2-0P-100A, Standby Diesel Generators JPM P-lA Page 2 of 16 NRC March 2014

.JJOI'lt venture of J 0

-::,eDF NINE MILE POINT NUCLEAR STATION Instructor Information A. l PM Information

1. Description

a. This JPM tests the operator's ability to locally start and secure the Division 1 Emergency Diesel Generator.

b. This JPM is considered alternate path because after locally starting the Division 1 Emergency Diesel Generator, a low lube oil condition will occur. The operator will mitigate the event by manually shutting down the diesel. c. Note this JPM is written for the Division 1 Diesel. If plant conditions do not support entering the Division 1 Diesel Room, then an alternate JPM is available (JPM P-1B) to use for the Division 2 Diesel. 2. Task Information:

a. N2-264001, Perform Emergency Stop of Division 1 (2) Emergency Diesel Generator

b. K/A 264000, A4.04 3.7/3.7 3. Evaluation I Task Criteria Evaluation Method Simulate Evaluation Location Plant Time Critical Task No Alternate Path Yes LOD >1.0 Yes JPM P-1A Page 3 of 16 NRC March 2014 a

venture ol ] 0 =:llatfon t::,eDF NINE MILE POINT NUCLEAR STATION 4. Recommended Start Location a. Unit 2 WEC 5. JPM Setup (if required)

a. Prepare a copy of N2-0SP-EGS-M@001, Section 8.2. Include a copy of the precautions and limitations.

b. Print out a full copy of N2-0P-100A and N2-0SP-EGS-M@001 for use by the operators when they are preparing to perform the JPM. c. Additionally, prepare separate copies of N2-0P-100A, Section H.l.O. Do not hand this section out to the operator until cued by the JPM. d. Ensure each operator performing the JPM has or has access to a fully charged flashlight

e. Ensure a set of double hearing protection is available in the Diesel Room prior to performing this JPM. JPM P-lA Page 4 of 16 NRC March 2014 CENG. a JOI'lt venture of J NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM P-lA Page 5 of 16 NRC March 2014 NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INITIATING CUE START TIME Given:

The plant is at 100% power.

N2-0SP-EGS-M@001, Diesel Generator and Diesel Air Start Valve Operability Test is about to be performed for the Division 1 Diesel.

N2-0SP-EGS-M@001, Steps 8.2.1 through 8.2.6 have been completed

You are the Plant Operator in the Field assigned to support the Diesel Run. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Perform the Diesel Generator Regular Monthly Start and Load Test for the Division 1 Diesel per N2-0SP-EGS-M@001, Section 8.2. PERFORMANCE ACT. CODE EVALUATOR PIS INA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used lAW CNG-OP-1.01-2001, Communications and Briefings.

2. Obtain a copy of N2-0SP-EGS-M@001 and p SAT I UNSAT review I utilize the correct section of the procedure STD: Current version of N2-OSP-EGS-M@001 obtained and Section 8.2 referenced lAW CNG-PR-2.01-1000, Document Control. Evaluators Note: Step 3 must be completed prior to initialing any step within the provided surveillance procedure.

JPM P-1A Page 6 of 16 NRC March 2014 a JOint venture ol J NINE MILE POINT NUCLEAR STATION PERFORMANCE

3. Documents name, signature, and initial on Attachment 1, Test Personnel Signature and Initial Log. ACT. CODE EVALUATOR PIS INA p SAT I UNSAT STD: On Attachment 1 of the provided surveillance, documents name, signature, and initial. Procedure Note: All indications and controls are located at 2CES*IPNL406 unless otherwise specified.

4. At 2CES*IPNL407, GENERATOR CONTROL s SAT I UNSAT PANEL, verify Voltage Regulator Switch in AUTO. STD: At 2CES*IPNL407, Observes the Voltage Regulator Cue: The Voltage Regulator Switch is in Switch is already in AUTO. AUTO 5. At 2CES*IPNL406, ENGINE CONTROL PANEL, s *PASS/ FAIL place CONTROL MODE keylock switch in LOCAL AND ensure the white LOCAL STD: At 2CES*IPNL406, places indicating light is illuminated.

the CONTROL MODE keylock switch to LOCAL. Observes the Cue: The CONTROL MODE keylock switch is white LOCAL indicating light is in LOCAL and the white LOCAL illuminated.

indicating light is illuminated.

6. At 2CEC*PNL852, ELECTRIC CONTROL p SAT I UNSAT BOARD, perform the following:

Verify DIVISION 1 2EGS*EG1 START STD: Contacts the control room switch in Normal-After-STOP.

and asks/directs them to perform Step 8.2.9.

Verify 2ENS*SWG101-N1, NEUTRAL BREAKER 101-N1, closed.

Verify EMERGENCY DSL GEN 1 VOLTAGE REGULATOR MODE SELECT switch in AUTO. Cue: As the control room, acknowledge the direction to perform Step 8.2. 9. Inform the operator that Step 8.2.9 is complete.

JPM P-1A Page 7 of 16 NRC March 2014 a J01'1t venture of J NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE PIS INA EVALUATOR Procedure Note: In the following step when the EMERGENCY DSL GEN 1 PARALLEL switch is placed to ON, the REMOTE indicating light will illuminate for the CONTROL MODE switch at panel 2CES*IPNL406 resulting in dual LOCAL/REMOTE indication.

7. At 2CEC*PNL852, place EMERGENCY DSL GEN 1 PARALLEL switch to ON. Cue: As the control room, acknowledge the direction to perform Step 8.2.10. Inform the operator that Step 8.2.10 is complete.

Cue: The REMOTE indicating light is illuminated.

s SAT/ UNSAT STD: Contacts the control room and asks/directs them to perform Step 8.2.10. Once the step is completed, observes the REMOTE indicating fight is illuminated at 2CES*IPNL406 False negative results for IST test of air start valves can be received if Procedure Note: diesel air compressor(s) are running prior to taking data in the following step. 8. 9. Record 2EGA-PI1SA, STARTING AIR PRESS:

RED-L. RECEIVER

BLACK-R. RECEIVER Cue: Both receiver tanks read 245 psig. At 2CES*IPNL406, depress ENGINE CONTROL START pushbutton.

Cue: The ENGINE CONTROL START pushbutton has been depressed.

You hear the sound of the diesel starting up. It sounds like a normal start. s s SAT/ UNSAT STD: At 2EGA-PI15A, documents the pressures indicated in Step 8.2.11 *PASS I FAIL STD: At 2CES*PNL406, depresses the ENGINE CONTROL START pushbutton.

Ustens for a good start of the diesel. If the operator asks for indications for the Starting Air Pressure on 2EGA-Evaluator Note: PllSA, inform the operator that both the Red and Black indicators show 210 psig. JPM P-1A Page 8 of 16 NRC March 2014 ajOI'1tventureof J 0 NINE MILE POINT NUCLEAR STATION PERFORMANCE

10. At 2CES*IPNL407, GENERATOR CONTROL PANEL, observe the following Diesel Generator start indications:

Diesel Speed as indicated on 12ESI-2EGSA04, ENGINE SPEED, rises to about 600 RPM Cue: Diesel Speed indicates 600 RPM 11.

Generator Voltage as indicated on GVM-2EGPA22, VOLTS GENERATOR, rises to about 4160 A-C VOLTS Cue: Diesel Voltage indicates 4160 Volts 12.

Generator Frequency as indicated on FM-2EGPA22, FREQUENCY GENERATOR, rises to about 60 HERTZ Cue: Diesel Frequency indicates 60 Hertz 13.

Generator Field Current as indicated on GFAM-2EGPA21, AMPS FIELD, rises to about 91 DC AMPERES Cue: Generator Field Current has risen to 91 DC AMPS JPM P-1A Page 9 of 16 ACT. CODE EVALUATOR P/5/NA s SAT I UNSAT observes the diesel speed on the RPM meter indicates 600 RPM . s SAT I UNSAT observes the Diesel Voltage at 4160 Volts. s SAT I UNSAT observes the Diesel Frequency at 60 Hertz. s SAT I UNSAT observes the Generator Field Current has risen to 91 DC Amps. NRC March 2014 a J01r1l venture of---] Oi:::lltlon NINE MILE POINT NUCLEAR STATION 14. PERFORMANCE At 2CEC*PNL852, observe the following Diesel Generator start indications:

SWP*MOV66A, SERVICE WTR OUTLET, opens

Diesel Service Water Flow indicated on 2SWP*FI76A, SERVICE WTR FLOW, is GPM

Annunciator 852117, EDG 1 RUNNING, alarms Cue: As the control room, acknowledge the direction to perform Step 8.2.14. Inform the operator that Step 8.2.14 is complete ACT. CODE P/S/NA s EVALUATOR SAT/ UNSAT STD: Contacts the control room and asks/directs them to perform Step 8.2.14. Alternate Path: Once the diesel is up and running, the Evaluator will give a cue to the operator that there is an alarm at the Diesel Control Panel. The operator will respond and determine that a low oil pressure condition exists and the diesel should have shutdown automatically.

The operator will take action to manually shutdown the diesel. Procedure Note: JPM P-1A The cause of the low lube oil pressure condition must be corrected prior to restart of the Diesel Generator.

Page 10 of 16 NRC March 2014 CENG .. a JOI'l! ventl)re oi J 0 NINE MILE POINT NUCLEAR STATION PERFORMANCE

15. Cue: Inform the operator that there is an audible alarm coming from 2CES*IPNL406.

When the operator looks at the Annunciator tiles, inform the operator that Annunciator 406-1-1, Low Lube Oil Pressure Engine is alarming.

ARP for Annunciator 406-1-1: IF in the test mode, VERIFY that the automatic response occurs. Cue: Inform the operator that the diesel is still running and if asked for Lube Oil Pressure, inform him that lube oil pressure indication is 15 psig. Cue: Once the operator determines the diesel did not shutdown and should have, direct the operator to "Perform an Emergency Shutdown of the Division 1 Emergency Diesel IA W N2-0P-1 OOA, Section H.1. 0". Hand the operator the procedure section for N2-0P-1 OOA, Section H.1. 0. 16. IF Diesel Generator is in Test Mode, perform the following:

At 2CEC*PNL852, using GOVERNOR switch, reduce Diesel Generator Load to 100 KW.

Using VOLTAGE REGULATOR switch, adjust VARS to >0 AND <100 A-C KILOVARS TO BUS.

Open 2ENS*SWG101-1, OUTPUT BREAKER 101-1.

Continue at Step H.1.3 . Cue: If necessary as the control room, acknowledge the direction to perform N2-0P-100A, Step H.1.1. Inform the operator that Step H.1.1 is complete JPM P-1A Page 11 of 16 ACT. CODE EVALUATOR P/5/NA s SAT I UNSAT STD: Responds to the annunciator by referencing the ARP for 406-1-1. Determines the Diesel is operating in TEST MODE and should have shut down automatically.

Acknowledges direction to perform an emergency shutdown of the Division 1 EDG. s SAT I UNSAT STD: May determine this step is already complete as the diesel has not been loaded -or-may contact the control room and directs them to perform N2-0P-100A, Step H.1.1. NRC March 2014 CENG, a JOint venture ot---J 0 NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE PIS INA EVALUATOR Procedure Note: The following step will cause the Diesel Generator to stop immediately without a cooldown period. 17. At 2CES*IPNL406, ENGINE CONTROL PANEL, depress EMERGENCY STOP red STOP pushbutton.

Cue: The EMERGENCY STOP red STOP pushbutton has been depressed.

The diesel continues to run. s *PASS I FAIL STD: At 2CES*INPL406, depresses the EMERGENCY STOP pushbutton.

Determines the diesel did not stop. Evaluators Note: In order to shutdown the diesel, the operator is required to perform Step 17, 18, or 19. Performance of any one of the steps will cause the diesel to shutdown.

Once the operator decides on which method they would like to use to shutdown the diesel, the step must be graded. If the operator fails to perform that step correctly, then the step is graded as FAIL. The steps not performed are not required to be graded and may be marked as NA. For a description of each of the below methods see the evaluators job aide at the end of this JPM. 18. IF Diesel does NOT stop, perform one of the following:

Depress button AND pull Manual Fuel Control Quadrant Handle down AND hold down UNTIL Diesel Generator comes to a complete stop. Cue: The BUTTON has been depressed and MANUAL FUEL CONTROL QUADRANT HANDLE is down. The diesel is starting to coast down. Cue: After 5 seconds, as long as the operator continues to hold the handle down, provide the following cue "The diesel has come to a complete stop". JPM P-1A Page 12 of 16 s *PASS I FAIL INA STD: Depresses the Button and pulls the MANUAL FUEL CONTROL QUADRANT HANDLE down until the diesel comes to a complete stop. Once the diesel has stopped, releases the HANDLE. NRC March 2014 aJOWitventureol--J NINE MILE POINT NUCLEAR STATION 19. 20. PERFORMANCE Pull out latching rod of Overspeed Trip Valve at Overspeed Governor.

Cue: The LATCHING ROD of the OVERSPEED TRIP VALVE at the overspeed GOVERNOR has been PULLED. The diesel is coasting down. Trip Combustion Air Inlet Butterfly Valve closed by pulling Overspeed Governor output lever towards the Generator End with a 1" open ended wrench. (The action will force the output arm towards the Butterfly Valve.) Cue: A 1 inch open ended wrench has been obtained.

Cue: The OVERSPEED GOVERNOR OUTPUT LEVER has been PULLED towards the GENERATOR END. The COMBUSTION AIR INLET BUTTERFLY VALVE has been tripped. The diesel is coasting down. ACT. CODE PI 5/ NA s s EVALUATOR

PASS I FAIL I NA STD: Pulls the LATCHING ROD of the OVERSPEED TRIP VALVE at the overspeed governor.

PASS I FAIL I NA STD: Using a 1. inch wrench, trips the COMBUSTION AIR INLET BUTTERFLY VALVE closed by PULLING the OVERSPEED GOVERNOR OUTPUT LEVER towards the Generator END. Evaluators Note: Once the operator is informed that the diesel is coasting down, provide the following cue: TERMINATING CUE STOPTJ:ME JPM P-1A Cue: Your task is complete.

Another operator will complete any remaining actions. An Emergency Trip has been performed on the Division 1 Diesel. Page 13 of 16 NRC March 2014 CENG. ajoint\11f'lhxeof

--, 0=--I NINE MILE POINT NUCLEAR STATION Evaluator lob Aid Do Not Provide to Candidate Manual Fuel Control Quadrant Handle: JPM P-lA Page 14 of 16 Manual Fuel Handle (Push Button and Pull Down) NRC March 2014 a jcwlt venture of O=:;o--;:, eoF I NINE MILE POINT NUCLEAR STATION Evaluator lob Aid Do Not Provide to Candidate Overspeed Trip Valve and Combustion Air Inlet Butterfly Valve:

On the Walkway where the Diesel Connects to the Generator.

Looking over the railing straight down at the two trip devices. Combustion Air Inlet Butterfly Valve (Using Wrench, pull towards Generator end) JPM P-1A Page 15 of 16 Latching Rod of the Overspeed Trip Valve (Pull Out) NRC March 2014 CENG ... aJOI'Itventureoi--J 0 =: .. Hon t.J::eoF NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INITIATING CUE JPM P-1A JPM Handout Given:

The plant is at 100% power.

N2-0SP-EGS-M@001, Diesel Generator and Diesel Air Start Valve Operability Test is about to be performed for the Division 1 Diesel.

N2-0SP-EGS-M@001, Steps 8.2.1 through 8.2.6 have been completed

You are the Plant Operator in the Field assigned to support the Diesel Run. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Perform the Diesel Generator Regular Monthly Start and Load Test for the Division 1 Diesel per N2-0SP-EGS-M@001, Section 8.2. Page 16 of 16 NRC March 2014 CENG .. NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC Plant P-18 Revision:

2.0 -----Title: Local Start of Division 2 Diesel Generator (Alternate Path) Approvals:

Developed By Validated By Facility Reviewer Signature I Printed Name David Huff 02/11/2014 Mike Storms Approximate Duration:

Aaron Armstrong

\JI "' Tt ll to" 20 minutes 12/13/2013 2/;9/wt""-

Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

Date: JPM P-18 Page 1 of 16 NRC March 2014 CENG .. a JOI'lt venture of J NINE MILE POINT NUCLEAR STATION References

1. NS-OSP-EGS-M@OOl, Diesel Generator and Diesel Air Start Valve Operability Test -Division 1 and 2 2. N2-0P-100A, Standby Diesel Generators JPM P-lB Page 2 of 16 NRC March 2014 CENG ... a JOin: venture of ] 0 =:'lation NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to locally start and secure the Division 2 Emergency Diesel Generator.

b. This JPM is considered alternate path because after locally starting the Division 2 Emergency Diesel Generator, a low lube oil condition will occur. The operator will mitigate the event by manually shutting down the diesel. c. Note this JPM is written for the Division 2 Diesel. If plant conditions do not support entering the Division 2 Diesel Room, then an alternate JPM is available (JPM P-1A) to use for the Division 1 Diesel. 2. Task Information:

a. N2-264001, Perform Emergency Stop of Division 1 (2) Emergency Diesel Generator

b. K/A 264000, A4.04 3.7/3.7 3. Evaluation I Task Criteria Evaluation Method Simulate Evaluation Location Plant Time Critical Task No Alternate Path Yes LOD >1.0 Yes JPM P-18 Page 3 of 16 NRC March 2014 CENG. NINE MILE POINT NUCLEAR STATION 4. Recommended Start Location a. Unit 2 WEC 5. JPM Setup (if required)

a. Prepare a copy of N2-0SP-EGS-M@001, Section 8.2. Include a copy of the precautions and limitations.

b. Print out a full copy of N2-0P-100A and N2-0SP-EGS-M@001 for use by the operators when they are preparing to perform the JPM. c. Additionally, prepare separate copies of N2-0P-100A, Section H.l.O. Do not hand this section out to the operator until cued by the JPM. d. Ensure each operator performing the JPM has or has access to a fully charged flashlight

e. Ensure a set of double hearing protection is available in the Diesel Room prior to performing this JPM. JPM P-18 Page 4 of 16 NRC March 2014 a JOint venture of--::l NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM P-lB Page 5 of 16 NRC March 2014 aJOintventureol--FJ o=::*llt*'

NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INITIATING CUE START TIME Given:

The plant is at 100% power.

N2-0SP-EGS-M@001, Diesel Generator and Diesel Air Start Valve Operability Test is about to be performed for the Division 2 Diesel.

N2-0SP-EGS-M@001, Steps 8.2.1 through 8.2.6 have been completed

You are the Plant Operator in the Field assigned to support the Diesel Run. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Perform the Diesel Generator Regular Monthly Start and Load Test for the Division 2 Diesel per N2-0SP-EGS-M@001, Section 8.2. PERFORMANCE ACT. CODE EVALUATOR PIS INA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used lAW CNG-OP-1.01-2001, Communications and Briefings.

2. Obtain a copy of N2-0SP-EGS-M@001 and p SAT I UNSAT review I utilize the correct section of the procedure STD: Current version of N2-OSP-EGS-M@001 obtained and Section 8.2 referenced lAW CNG-PR-2.01-1000, Document Control. Eval.uators Note: Step 3 must be completed prior to initialing any step within the provided surveillance procedure.

JPM P-1B Page 6 of 16 NRC March 2014 a )Otr<t venture of---, O=:""'lon NINE MILE POINT NUCLEAR STATION PERFORMANCE

3. Documents name, signature, and initial on Attachment 1, Test Personnel Signature and Initial Log. ACT. CODE EVALUATOR PI 5 INA p SAT I UNSAT STD: On Attachment 1 of the provided surveillance, documents name, signature, and initial. Procedure Note: All indications and controls are located at 2CES*IPNL408 unless otherwise specified.

4. At 2CES*IPNL412, GENERATOR CONTROL s SAT I UNSAT PANEL, verify Voltage Regulator Switch in AUTO. STD: At 2CES*IPNL412, Observes the Voltage Regulator Cue: The Voltage Regulator Switch is in Switch is already in AUTO. AUTO 5. At 2CES*IPNL408, ENGINE CONTROL PANEL, s *PASS I FAIL place CONTROL MODE keylock switch in LOCAL AND ensure the white LOCAL STD: At 2CES*IPNL408, places indicating light is illuminated.

the CONTROL MODE key/ock switch to LOCAL. Observes the Cue: The CONTROL MODE keylock switch is white LOCAL*indicating light is in LOCAL and the white LOCAL illuminated.

indicating light is illuminated.

6. At 2CEC*PNL852, ELECTRIC CONTROL p SAT I UNSAT BOARD, perform the following:

Verify DIVISION 2 2EGS*EG3 START STD: Contacts the control room switch in Normal-After-STOP.

and asks/directs them to perform Step 8.2.9.

Verify 2ENS*SWG103-N1, NEUTRAL BREAKER 103-N1, closed.

Verify EMERGENCY DSL GEN 3 VOLTAGE REGULATOR MODE SELECT switch in AUTO. Cue: As the control room, acknowledge the direction to perform Step 8.2. 9. Inform the operator that Step 8.2. 9 is complete.

JPM P-1B Page 7 of 16 NRC March 2014 CENG" a JOI'lt venture 0 Constellation

... * .. eoF I Energy ..,,. . NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE PI 5 INA EVALUATOR Procedure Note: In the following step when the EMERGENCY DSL GEN 3 PARALLEL switch is placed to ON, the REMOTE indicating light will illuminate for the CONTROL MODE switch at panel 2CES*IPNL408 resulting in dual LOCAL/REMOTE indication.

7. At 2CEC*PNL852, place EMERGENCY DSL GEN 3 PARALLEL switch to ON. Cue: As the control room, acknowledge the direction to perform Step 8.2.10. Inform the operator that Step 8.2.10 is complete.

Cue: The REMOTE indicating light is illuminated.

s SAT I UNSAT STD: Contacts the control room and asks/directs them to perform Step 8.2.10. Once the step is completed, observes the REMOTE indicating light is illuminated at 2CES*IPNL408 False negative results for 1ST test of air start valves can be received if Procecture Note: diesel air compressor(s) are running prior to taking data in the following step. 8. Record 2EGA-PI15B, STARTING AIR PRESS: s SAT I UNSAT

RED-L. RECEIVER

BLACK-R. RECEIVER STD: At 2EGA-PI15B, documents the pressures Cue: Both receiver tanks read 245 psig. indicated in Step 8.2.11 9. At 2CES*IPNL408, depress ENGINE s *PASS/ FAIL CONTROL START pushbutton.

STD: At 2CES*PNL408, Cue: The ENGINE CONTROL START depresses the ENGINE pushbutton has been depressed.

You CONTROL START pushbutton.

hear the sound of the diesel starting Listens for a good start of the up. It sounds like a normal start. diesel. If the operator asks for indications for the Starting Air Pressure on 2EGA-Evaluator Note: PllSB, inform the operator that both the Red and Black indicators show 210 psig. JPM P-1B Page 8 of 16 NRC March 2014 CENG." a joint ventureof---

0=:"--;;,eo* \ NINE MILE POINT NUCLEAR STATION PERFORMANCE

10. At 2CES*IPNL412, GENERATOR CONTROL PANEL, observe the following Diesel Generator start indications:

Diesel Speed as indicated on 12ESI-2EGSB04, ENGINE SPEED, rises to about 600 RPM Cue: Diesel Speed indicates 600 RPM 11.

Generator Voltage as indicated on GVM-2EGPB22, VOLTS GENERATOR, rises to about 4160 A-C VOLTS Cue: Diesel Voltage indicates 4160 Volts 12.

Generator Frequency as indicated on FM-2EGPB22, FREQUENCY GENERATOR, rises to about 60 HERTZ Cue: Diesel Frequency indicates 60 Hertz 13.

Generator Field Current as indicated on GFAM-2EGPB21, AMPS FIELD, rises to about 91 DC AMPERES Cue: Generator Field Current has risen to 91 DC AMPS JPM P-16 Page 9 of 16 ACT. CODE EVALUATOR PIS/ NA s SAT I UNSAT STD: At 2CES*PNL412, observes the diesel speed on the RPM meter indicates 600 RPM . s SAT I UNSAT STD: At 2CES*PNL412, observes the Diesel Voltage at 4160 Volts. s SAT I UNSAT STD: At 2CES*PNL412, observes the Diesel Frequency at 60 Hertz. s SAT I UNSAT STD: At 2CES*PNL412, observes the Generator Field Current has risen to 91 DC Amps. NRC March 2014 CENG .. a JOI'lt venlu'B of---, o= ....... .;,eDF I NINE MILE POINT NUCLEAR STATION 14. PERFORMANCE At 2CEC*PNL852, observe the following Diesel Generator start indications:

SWP*MOV66B, SERVICE WTR OUTLET, opens

Diesel Service Water Flow indicated on 2SWP*FI76), SERVICE WTR FLOW, is GPM

Annunciator 852217, EDG 3 RUNNING, alarms Cue: As the control room, acknowledge the direction to perform Step 8.2.14. Inform the operator that Step 8.2.14 is complete ACT. CODE PIS INA s EVALUATOR SAT I UNSAT STD: Contacts the control room and asks/directs them to perform Step 8.2.14. Alternate Path: Once the diesel is up and running, the Evaluator will give a cue to the operator that there is an alarm at the Diesel Control Panel. The operator will respond and determine that a low oil pressure condition exists and the diesel should have shutdown automatically.

The operator will take action to manually shutdown the diesel. Procedure Note: JPM P-1B The cause of the low lube oil pressure condition must be corrected prior to restart of the Diesel Generator.

Page 10 of 16 NRC March 2014 a JOint venture of--::l NINE MILE POINT NUCLEAR STATION PERFORMANCE

15. Cue: Inform the operator that there is an audible alarm coming from 2CES*IPNL408.

When the operator looks at the Annunciator tiles, inform the operator that Annunciator 408-1-1, Low Lube Oil Pressure Engine is alarming.

ARP for Annunciator 408-1-1: IF in the test mode, VERIFY that the automatic response occurs. Cue: Inform the operator that the diesel is still running and if asked for Lube Oil Pressure, inform him that lube oil pressure indication is 15 psig. Cue: Once the operator determines the diesel did not shutdown and should have, direct the operator to "Perform an Emergency Shutdown of the Division 2 Emergency Diesel IA W N2-0P-1 OOA, Section H.1. 0". Hand the operator the procedure section for N2-0P-100A, Section H.1. 0. 16. IF Diesel Generator is in Test Mode, perform the following:

At 2CEC*PNL852, using GOVERNOR switch, reduce Diesel Generator Load to 100 KW.

Using VOLTAGE REGULATOR switch, adjust VARS to >0 AND <100 A-C KILOVARS TO BUS.

Open 2ENS*SWG103-14, OUTPUT BREAKER 103-14.

Continue at Step H.1.3 . Cue: If necessary as the control room, acknowledge the direction to perform N2-0P-100A, Step H.1.1. Inform the operator that Step H.1.1 is complete JPM P-1B Page 11 of 16 ACT. CODE EVALUATOR PI Sf NA s SAT I UNSAT STD: Responds to the annunciator by referencing the ARP for 408-1-1. Determines the Diesel is operating in TEST MODE and should have shut down automatically.

Acknowledges direction to perform an emergency shutdown of the Division 2 EDG. s SAT I UNSAT STD: May determine this step is already complete as the diesel has not been loaded -or-may contact the control room and directs them to perform N2-0P-100A, Step H.1.1. NRC March 2014 a]Ointventureof

__ _ 0 =:ll.tlon i NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE PIS INA EVALUATOR Procedure Note: The following step will cause the Diesel Generator to stop immediately without a cooldown period. 17. At 2CES*IPNL408, ENGINE CONTROL PANEL, depress EMERGENCY STOP red STOP pushbutton.

Cue: The EMERGENCY STOP red STOP pushbutton has been depressed.

The diesel continues to run. s *PASS/ FAIL depresses the EMERGENCY STOP pushbutton.

Determines the diesel did not stop. 1 .* Evaluators Note: In order to shutdown the diesel, the operator is required to perform Step 17, 18, or 19. Performance of any one of the steps will cause the diesel to shutdown.

Once the operator decides on which method they would like to use to shutdown the diesel, the step must be graded. If the operator fails to perform that step correctly, then the step is graded as FAIL. The steps not performed are not required to be graded and may be marked as NA. For a description of each of the below methods see the evaluators job aide at the end of this JPM. 18. IF Diesel does NOT stop, perform one of the following:

Depress button AND pull Manual Fuel Control Quadrant Handle down AND hold down UNTIL Diesel Generator comes to a complete stop. Cue: The BUTTON has been depressed and MANUAL FUEL CONTROL QUADRANT HANDLE is down. The diesel is starting to coast down. Cue: After 5 seconds, as long as the operator continues to hold the handle down, provide the following cue "The diesel has come to a complete stop". JPM P-18 Page 12 of 16 s *PASS I FAIL INA STD: Depresses the Button and pulls the MANUAL FUEL CONTROL QUADRANT HANDLE down until the diesel comes to a complete stop. Once the diesel has stopped, releases the HANDLE. NRC March 2014 CENGW a JOint venture ol--::l o=:latlon NINE MILE POINT NUCLEAR STATION 19. 20. PERFORMANCE Pull out latching rod of Overspeed Trip Valve at Overspeed Governor.

Cue: The LATCHING ROD of the OVERSPEED TRIP VALVE at the overspeed GOVERNOR has been PULLED. The diesel is coasting down. Trip Combustion Air Inlet Butterfly Valve closed by pulling Overspeed Governor output lever towards the Generator End with a 1" open ended wrench. (The action will force the output arm towards the Butterfly Valve.) Cue: A 1 inch open ended wrench has been obtained.

Cue: The OVERSPEED GOVERNOR OUTPUT LEVER has been PULLED towards the GENERA TOR END. The COMBUSTION AIR INLET BUTTERFLY VALVE has been tripped. The diesel is coasting down. ACT. CODE PIS/ NA s s EVALUATOR

PASS I FAIL STD: Pulls the LATCHING ROD of the OVERSPEED TRIP VALVE at the overspeed governor.

PASS I FAIL STD: Using a 1 inch wrench, trips the COMBUSITON AIR INLET BUTTERFLY VALVE closed by PUI..LING the OVERSPEED GOVERNOR OUTPUT LEVER towards the Generator END. Evaluators Note: Once the operator is informed that the diesel is coasting down, provide the following cue: TERMINATING CUE STOP TIME JPM P-1B Cue: Your task is complete.

Another operator wi/1 complete any remaining actions. An Emergency Trip has been performed on the Division 2 Diesel. Page 13 of 16 NRC March 2014 a pnt venture of---, 0=--J': eDF I NINE MILE POINT NUCLEAR STATION Evaluator lob Aid Do Not Provide to Candidate Manual Fuel Control Quadrant Handle: JPM P-lB Page 14 of 16 Manual Fuel Handle (Push Button and Pull Down) NRC March 2014 CENG. ajolntventueof 0=:-I NINE MILE POINT NUCLEAR STATION Evaluator lob Aid Do Not Provide to Candidate Overspeed Trip Valve and Combustion Air Inlet Butterfly Valve:

On the Walkway where the Diesel Connects to the Generator.

Looking over the railing straight down at the two trip devices. Combustion Air Inlet Butterfly Valve (Using Wrench, pull towards Generator end) JPM P-1B Page 15 of 16 Latching Rod of the Overspeed Trip Valve (Pull Out) NRC March 2014 aJOI'll venture oi I

-:,',eoF NINE MILE POINT NUCLEAR STATION INITIAL CONDmONS INmATING CUE JPM P-1B JPM Handout Given:

The plant is at 100% power.

N2-0SP-EGS-M@001, Diesel Generator and Diesel Air Start Valve Operability Test is about to be performed for the Division 2 Diesel.

N2-0SP-EGS-M@001, Steps 8.2.1 through 8.2.6 have been completed

You are the Plant Operator in the Field assigned to support the Diesel Run. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Perform the Diesel Generator Regular Monthly Start and Load Test for the Division 2 Diesel per N2-0SP-EGS-M@001, Section 8.2. Page 16 of 16 NRC March 2014 CENG NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC Plant P-2 Revision:

1.0 __.:__.:._

__ _ Title: Isolate a Hydraulic Control Unit with Cooling Water Approvals:

Signature I Printed Name Developed By David Huff 02/11/2013 Validated By Mike Storms 12/13/2013 Facility Reviewer Aaron Armstrong Approximate Duration:

20 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

Date: JPM P-2 Page 1 of 9 NRC March 2014 NINE MILE POINT NUCLEAR STATION References

1. N2-0P-30, Control Rod Drive JPM P-2 Page 2 of 9 NRC March 2014 CENG ... a)Oinl ventureof--

o=llotlon I NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to isolate a Hydraulic Control Unit With Cooling Water. 2. Task Information:

a. N2-201001-04006, Isolate a Hydraulic Control Unit b. K/A 203000, A2.02 3.5/3.5 3. Evaluation I Task Criteria Evaluation Method Simulate Evaluation Location Plant Time Critical Task No Alternate Path No LOD >1.0 Yes 4. Recommended Start Location a. Unit 2 WEC 5. JPM Setup (if required)

a. Prepare a copy of N2-0P-30, Section 8.0. Include a copy of the precautions and limitations and the page after the end of the procedure section. b. Ensure each operator has or has access to a fully charged flashlight.

JPM P-2 Page 3 of 9 NRC March 2014 CENG.N a JOI'll venture o: i 0 =:ttation

.;,eoF I NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM P-2 Page 4 of 9 NRC March 2014 ajOI'ltventureot-----, 0 =""""" -:.*,eoF I NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INITIATING CUE START TIME Given:

The plant is at 100% power.

Rod 22-59 is stuck at position 10 and has been declared inoperable.

The CRS has determined HCU 22-59 needs to be isolated.

2RDS-P1A is in service.

No other HCUs are currently isolated.

Maintenance is not going to be performed on HCU 22-59 and it will not be isolated for an extended period of time.

A drain line has been installed for HCU 22-59 at 2RDS*V107 and the drain line has been routed to an appropriate floor drain. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions

{Operators Name), Isolate HCU 22-59 with cooling water per N2-0P-30, Section F.B.O. PERFORMANCE ACT. CODE EVALUATOR PIS/ NA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used lAW CNG-OP-1.01-2001, Communications and Briefings.

2. Obtain a copy of N2-0P-30 and review I p SAT I UNSAT utilize the correct section of the procedure STD: Current version of N2-0P-30 obtained and Section 8.2 referenced lAW CNG-PR-2.01-1000, Document Control. Procedure Where XX-YY appears, XX-YY is the number of the HCU being manipulated.

JIIOte: JPM P-2 Page 5 of 9 NRC March 2014 CENG, a)o"t'eotuceol I

NINE MILE POINT NUCLEAR STATION Procedure Note: Procedure Note: PERFORMANCE ACT. CODE PIS/ NA EVALUATOR

Isolating an HCU without cooling water should be performed when reactor water temperature is less than 200°F, or isolating an HCU without cooling water when reactor water temperature is greater than 200°F should be minimized (less than one shift duration) or seal degradation could occur.

When returning an isolated HCU to service, extreme care must be taken. Restore cooling water slowly or thermal shock and seal damage could occur.

Isolating HCUS with 2RDS*V101(XX-YY) or 2RDS*V104(XX-YY) closed raises the Cooling Water Differential Pressure.

A Cooling Water Differential Pressure of 35 psid is sufficient to operate the Collet Piston and unlatch Control Rods which could result in unplanned Control Rod withdrawals.

Isolating more than 80 HCUs with a CRD Pump in service could raise Cooling Water Differential Pressure to psid and result in unplanned Control Rod withdrawals.

Refer to INPO SEN 264. [C12]

The following step is to be performed to prevent control rod movement, not for maintenance.

A withdrawn control rod that is stuck should be disarmed hydraulically, preferably with cooling water flow, per the following step (hydraulically disarming a withdrawn control rod that is stuck is required in accordance with Technical Specification 3.1.3). 3. IF an RDS Pump is in service, verify :579 HCUs are isolated.

s SAT I UNSAT 4. JPM P-2 Close 2RDS*V101, (XX-YY) Insert Isolation.

Cue: 2RDS*V101 is closed. Page 6 of 9 s STD: Determines per the turnover that 2RDS-P1A is in service and no additional HCUs are isolated.

PASS/ FAIL STD: At HCU22-59, Closes 2RDS*V101 by rotating the hand wheel in the clockwise direction until the valve is seated. NRC March 2014 a10"1 "otcco ol I

.._,*,eoF NINE MILE POINT NUCLEAR STATION PERFORMANCE

5. Close 2RDS*V102, (XX-YY) Withdraw Isolation.

Cue: 2RDS*V102 is closed. 6. Close 2RDS-v113, (XX-YY) Charging Water Isolation.

Cue: 2RDS*V113 is closed. ACT. CODE EVALUATOR P/5/NA s *PASS I FAIL STD: At HCU 22-59, Closes 2RDS*V102 by rotating the hand wheel in the .clockwise direction until the valve is seated. s *PASS( FAIL STD: At HCU 22-59, Closes 2RDS*V113 by rotating the hand wheel in the clockwise direction until the valve is seated. Procedure Rx water will drain out of 2RDS*V107 if a Reactor Scram occurs. caution: 7. Using thread lubricant, (Locktite 58031 -s SAT I UNSAT symbol number 95-74-180), ATTACH drain STD: Determines per the line to HCU at 2RDS*V107, (XX-YY) Accumulator Drain AND route to turnover that this step is floor/equipment drain. (Lubricant use N/A for complete.

Swagelok Fittings)

8. Slowly open 2RDS*V107 (XX-YY) to s *PASS I FAIL depressurize accumulator.

STD: At HCU 22*59, slowly Cue: 2RDS*V107 is open. The accumulator opens 2RDS*V107 by rotating is depressurized.

the hand wheel in the counter clockwise direction until the accumulator is fully depressurized.

9. Close 2RDS*V107 (XX-YY). s *PASS I FAIL Cue: 2RDS*V107 is closed. STD: At HCU 22-59, Closes 2RDS*V107 by rotating the hand wheel in the clockwise direction until the valve is seated. JPM P-2 Page 7 of 9 NRC March 2014 a joint ventu91:>81:>4 (E)mergency or abnormal in-plant (EN)gineered safety feature -I -I (control room system) (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams ::; 31::; 3 I::; 2 (randomly selected) (R)CA (S)imulator

NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC Plant P-3 Title: Align Firewater to RHS B Approvals:

Developed By Validated By Facility Reviewer Revision:

0.0 --=.::...=....

__ _ Printed Name Mike Storms 12/13/2013 Aaron Armstrong Approximate Duration:

20 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

Date: JPM P-3 Page 1 of 9 NRC March 2014 aJolnlventureof---

NINE MILE POINT NUCLEAR STATION References

1. N2-EOP-6.6, RHR Fire Water Cross-Tie JPM P-3 Page 2 of 9 NRC March 2014 CENG,. a]Ointventureof--

o=llatlan

-:,eoF I NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to align Fire Water to the RHS System. 2. Task Information:

a. N2-EOP06-01001-06, Implement N2-EOP-6.6, Cross-Tie RHR Fire Water System b. K/A 203000, A2.02 3.5/3.5 3. Evaluation I Task Criteria Evaluation Method Simulate Evaluation Location Plant Time Critical Task No Alternate Path No LOD >1.0 Yes 4. Recommended Start Location a. Unit 2 WEC 5. JPM Setup (if required)

a. Prepare a copy of N2-EOP-6.6, Section 6.2. Include a copy of the precautions and limitations.

JPM P-3 Page 3 of 9 NRC March 2014 CENG .. a JOin"enturo of I -::,eDF NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM P-3 Page 4 of 9 NRC March 2014 a JOint venture of---, 0 =:'"'ion I NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS Given:

A LOCA has occurred.

The CRS has determined Fire Water is needed for injection into the RPV via RHS B.

N2-EOP-6.6, Steps 6.2.1 through 6.2.5 have been completed.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions INITIATING CUE (Operators Name), Align Fire Water to RHS Loop B per N2-EOP-6.6, Section 6.2. START TIME PERFORMANCE ACT. CODE EVALUATOR PI 5 INA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used JAW CNG-OP-1.01-2001, Communications and Briefings.

2. Obtain a copy of N2-EOP-6.6 and review I p SAT I UNSAT utilize the correct section of the procedure.

STD: Current version of N2-EOP-6. 6 obtained and Section 6.2 referenced JAW CNG-PR-2.01-1000, Document Control. 3. Verify closed 2CNS-v622, CNS TO RHR s SAT I UNSAT SUPPLY ISOL (Rx Bldg, EL289 Southside STD: Checks 2CNS-V622 is across from CRD maintenance room) closed by rotating the hand Cue: 2CNS-V622 is closed. wheel in the clockwise direction and observing no movement.

JPM P-3 Page 5 of 9 NRC March 2014 CENG,. a ]Oint venture 0="""'"

I NINE MILE POINT NUCLEAR STATION 4. PERFORMANCE Verify closed 2RHS*V79, CONDENSATE FLUSH TO HEAD SPRAY HDR ISOL. (Rx Bldg EL 289) Cue: 2RHS*V79 is closed. ACT. CODE PI 5 INA s EVALUATOR SAT I UNSAT STD: Checks 2RHS*V79 is closed by rotating the hand wheel in the clockwise direction and observing no movement.

Proced:ure Caution: Residual pressure may exist when removing the test connection blind flange between valves 2CNS-V622 and 2RHS*V79 (Figure 4). E"aluators Note Several of the remaining steps require specific tools and/or equipment from the EOP Gang Box Located on RB 289'. The operator should show the evaluator where the gang box is, but SHOULD NOT open the gang box or break the inventory seal for any step in this JPM. As necessary the evaluator may question the operator as to what tools he/she is obtaining from the box. 5. 6. JPM P-3 Remove test connection blind flange from between valves 2CNS-V622 AND 2RHS*V79 (Figure 4). (Rx Bldg EL 289) Cue: Blank Flange is removed. Install 2V2" firehose adapter to test connection flange (Figure 4). (Rx Bldg EL 289) Cue: The 2.5" firehose adapter to test connection flange is installed.

Page 6 of 9 s s *PASS I FAIL STD: Identifies that tools are . ' needed from the EOP Gang Box. Simulates obtaining the tools and simulat,es.

using the tools to remove the blank flange downstream of V622. *PASS/ FAIL STD: Ide,ntlftes that tools are needed from the. EOP Gang Box. Simulates obtaining the tools and simulates installing the firehose adapter to test connection NRC March 2014 a JOint venture of---, o=--;:,eDF I NINE MILE POINT NUCLEAR STATION 7. PERFORMANCE Connect male end of 2V2" firehose from EOP gangbox, to test connection flange adapter(Figure 4). (Rx Bldg EL 289 Cue: The male end of the 2.5" firehose is connected to the test connection flange adapter. ACT. CODE PIS/ NA s EVALUATOR

PASS I FAIL STD: Identifies.

that.tools are needed from the EOP .Gang Box. Simulates obtaining the tools and slmuJatl:i!s connecting the firehose to the teSt connection flange adaptef'.

Procedure Note: FHR 78 (Rx Bldg EL 289 near South stairwell entrance)

OR FHR 86 (Rx Bldg EL 289 Across from SLS Tank) may be used to supply firewater to RHS B. 8. 9. 10. JPM P-3 N2-EOP-6.6 allows the operator to lineup fire water from either FHR 78 or FHR 86. The operator may choose either one. Align firewater supply to RHR B via test connection flange adapter as follows: (Rx Bldg, EL 289, near South stairwell entrance)

Disconnect firehose at FHR 78 OR FHR 86 Cue: The firehose is disconnected from FHR 78(86)

Connect 2Y2" EOP firehose from test connection flange adapter, to FHR 78 OR FHR 86 Cue: The EOP firehose is connected to FHR 78(86)

Open 2FPW-v375, FHR 78 ANGLE VALVE OR 2FPW-v383, FHR 86 ANGLE VALVE Cue: 2FPW-V375 -or-2FPW-V383 is open. The firehose is pressurizing.

Page 7 of 9 s s s *PASS./ FAIL STD: At FHR 78 or 86, disconnects the firehose by rotating the union connection in the counter clockwise direction.

PASS/ FAIL STD: Simulates routing the EOP firehosefrom the test connection flange to FHR 78 or 86. Connl:i!cts the firehose to FHR 78 or 86 by rotating the union in the clockwise direction.

PASS I FAIL STD: Opens. 2FPW-V375 -or-2FPW-V383 by rotating the hand wheel if! the. countl:i!r clockwise direction until the is open. NRC March 2014 a JO'CI vectcce ot I NINE MILE POINT NUCLEAR STATION PE.RFOIUIANCE

11. Unlock AND open 2RHS*V79. (Rx Bldg EL

289) Cue: 2RHS*V79 is open. < ACT. CODE EVALUATOR P/5/NA ; ' s *PASS l FAlL STD: Opet)s 2RHS*V79 by rotating the band wheel in.the counterd<ickwise.direction until the valve is open.

CUE The firehose has been connected to the test flange and is pressurized.

2RHS*V79 is open. STOP TIME JPM P-3 Page 8 of 9 NRC March 2014 a 101nt 'enturn of I NINE MILE POINT NUCLEAR STATION IrnnAL CONDitiONS INinATING CUE JPM P-3 JPM Handout Given:

A LOCA has occurred.

The CRS has determined Fire Water is needed for injection into the RPV via RHS B.

N2-EOP-6.6, Steps 6.2.1 through 6.2.5 have been completed.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Align Fire Water to RHS Loop B per N2-EOP-6.6, Section 6.2. Page 9 of 9 NRC March 2014

CENG, MILE POINT NUCLEAR STATION Training Id: 2013 NRC RO Admin C0-1 Revision:

1.0 Title

Determine Containment Water Level Approvals:

Developed By Signature I Printed Name 4--David Huff Validated By Jerry Randall Facility Reviewer Aaron Armstrong Approximate Duration:

30 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Grade: Comments:

Evaluators Signature:

Stop Time: Pass I Fail Completion Time Date: -----02/14/2014 12/13/2013 JPM RO CO-l Page 1 of 10 NRC March 2014 NINE MILE POINT NUCLEAR STATION References

1. N2-EOP-6.23, Containment Water Level Determination JPM RO CO-l Page 2 of 10 NRC March 2014 CENG .. a JOint venture of-=::l o=:llatlon NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operators ability to determine Containment Water Level when containment level is above 224 feet. 2. Task Information:

a. N2-EOP06-01001-23, Implement N2-EOP-6.23, Containment Level Determination.

b. 2.1.25 (3.9) Ability to interpret reference materials, such as graphs, curves, tables, etc. 3. Evaluation I Task Criteria Evaluation Method Perform Evaluation Location Classroom Time Critical Task No Alternate Path No LOD >1.0 Yes 4. Recommended Start Location a. Training Classroom

5. JPM Setup (if required)

a. Ensure book carts are available for the operators to use and that there is an up to date copy of N2-EOP-6.23.

b. Ensure a calculator is available for each operator.

JPM RO C0-1 Page 3 of 10 NRC March 2014 CENG, a)OII"'lt ventureof--

'4*a NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM RO CO-l Page 4 of 10 NRC March 2014 a JOint venture of-:--=-1 O=:'lat\on NINE MILE POINT NUCLEAR SlATION INITIAL CONDITIONS INITIATING CUE START TIME Given:

Approximately one day ago the plant experienced a large break LOCA

In order to maintain adequate core cooling, operators have been injecting into the RPV with systems whose suction source is outside the primary containment.

The EOP Director has been monitoring the Primary Containment Pressure Limit (PCPL) per N2-EOP-RPV.

Primary Containment Water Level has just exceeded 224 feet

The EOP Director has directed the performance of N2-EOP-6.23, Containment Level Determination.

Steps 6.1 through 6.6 have been completed.

The EOP Director has determined Primary Containment Water Level is to be logged every 30 minutes.

You are the RO assigned to determine and log Containment Water Level per N2-EOP-6.23.

Another operator has been assigned to monitor the Fuel Zone Level Instruments.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Given the plant parameters found on the provided log, document the Primary Containment Water Level (PCWL) for 06:00 to 10:00. Additionally, on the log provided, document any required actions based on PCWL trend. Another operator will be taking care of all actions for monitoring the Fuel Zone instruments.

PERFORMANCE ACT. CODE EVALUATOR PIS INA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used lAW CNG-OP-1.01-2001, Communications and Briefings.

JPM RO CO-l Page 5 of 10 NRC March 2014 a)o,ntventure NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE PIS/ NA EVALUATOR

2. Obtain a copy of the reference material and review I utilize the correct section of the procedure.

p SAT I UNSAT STD: Obtains N2-EOP-6.23 Evaluators Note: The Answer Key attached to this JPM provides the grading criteria for the below step. Documentation of the correct .6.P is not required for successful completion of the below step. The operator need only determine the correct Primary Containment Water Level within +/- 1 foot in order to meet the intent of the critical step. 3. Using N2-EOP-6.23, Step 6.7 and Figure la, determines containment water level. p *PASS I FAIL STD: calculates the IJP by subtracting Suppression Chamber Pressure from Primary Containment Inlet N2 Pressure.

Uses the IJP to determine PCWL on Figure 1a. Documents the PCWL on the provided LOG. PCWL values have to be within :I: 1 foot of the value on the answer key. Documents ALL PCWL's from 06:00 to 10:00 on the provided Jog. The operator should notice that the .6.P between 08:00 and 09:30 has remained Evaluators the same and RPV injection flow has been constant.

The operator should identify Note: that Step 6.10 now applies and that the EOP DIRECTOR should be notified of a constant PCWL with no change in injection.

Evaluators Note: Evaluators Note: JPM RO CO-l If the operator informs the EOP DIRECTOR of the constant .6.P before completion of all PCWL logs, provide the following cue: Cue: The EOP DIRECTOR has been informed, continue logging all PCWL's through 10:00. Ensure you document your notification on the log. The critical aspect of the below step is for the operator to determine the EOP DIRECTOR needs to be notified of a constant PCWL with continuous injection.

It is not necessary to get the exact time frame documented to pass the below step. Page 6 of 10 NRC March 2014 CENG," a jOint venture NINE MILE POINT NUCLEAR STATION PERFORMANCE

4. When logging the PCWL, determines the LlP has not changed but RPV injection flow has remained constant.

Informs the EOP DIRECTOR.

ACT. CODE EVALUATOR PIS/ NA p *PASSJ FAIL

STD: Informs the EOP DIRECTOR that the I1P has not changed but RPV Injection has remained the, same. Documents the need to inf()rm the EOP DIRECTOR on the provided log. TERMINATING CUE The Operator logged all PCWL readings through 10:00 and documents the need to inform the EOP DIRECTOR of the constant LJ.P with continuous injection.

STOP TIME JPM RO CO-l Page 7 of 10 NRC March 2014 a JOI'll venture of-:--=-1 o=:llatlon NINE MILE POINT NUCLEAR STATION RPV Time Injection Flow 6:00 Constant 6:30 Constant 7:00 Constant 7:30 Constant 8:00 Constant 8:30 Constant 9:00 Constant 9:30 Constant 10:00 Constant Injection 2CMS*PI7A SUPPR Temperature CHAMBER PRESS OF PSIG 68 20 68 22 68 22 68 15 68 17 68 20 69 23 69 26 69 32 2CPS-PI127, PRIMARY CONTMT AP INLET N2 PRESS PSIG PSID 20 0 21 1 20 2 12.5 2.5 13.5 3.5 16.5 3.5 19 4 21 5 26.5 5.5 Are any actions required to be taken based on the above readings?

Document any actions required here: Inform the EOP Director that the 4P was constant with a constant injection rate for a period of time Feet 224 +/- 1 226 +/- 1 228 +/- 1 230 +/- 1 232 +/- 1 232 +/- 1 234 +/- 1 236 +/- 1 238 +/- 1 JPM RO C0-1 Page 8 of 10 NRC March 2014 NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INITIATING CUE JPM RO CO-l JPM Handout Given:

Approximately one day ago the plant experienced a large break LOCA

In order to maintain adequate core cooling, operators have been injecting into the RPV with systems whose suction source is outside the primary containment.

The EOP Director has been monitoring the Primary Containment Pressure Limit (PCPL) per N2-EOP-RPV.

Primary Containment Water Level has just exceeded 224 feet

The EOP Director has directed the performance of N2-EOP-6.23, Containment Level Determination.

Steps 6.1 through 6.6 have been completed.

The EOP Director has determined Primary Containment Water Level is to be logged every 30 minutes.

You are the RO assigned to determine and log Containment Water Level per N2-EOP-6.23.

Another operator has been assigned to monitor the Fuel Zone Level Instruments.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Given the plant parameters found on the provided log, document the Primary Containment Water Level (PCWL) for 06:00 to 10:00. Additionally, on the log provided, document any required actions based on PCWL trend. Another operator will be taking care of all actions for monitoring the Fuel Zone instruments.

Page 9 of 10 NRC March 2014

e 10 ,t ,entuce ol I 0 ConsteUauon

.. * ... eoF Energy "'"" NINE MILE POINT NUCLEAR STATION Time I RPV Injection Flow 6:00 Constant 6:30 Constant 7:00 Constant 7:30 Constant 8:00 Constant 8:30 Constant 9:00 Constant 9:30 Constant 10:00 Constant Injection Temperature OF 68 68 68 68 68 68 69 69 69 2CMS*PI7A SUPPR 2CPS-PI127, CHAMBER PRESS PRIMARY CONTMT INLET N2 PRESS PSIG PSIG 20 20 22 21 22 20 15 12.5 17 13.5 20 16.5 23 19 26 21 32 26.5 Are any actions required to be taken based on the above readings?

Document any actions required here: JPM RO CO-l Page 10 of 10 6P Primary Containment Water level PSID Feet NRC March 2014

M!LE POiNT r-.:UCLEAR STATION Training Id: 2013 NRC RO Admin C0-2 Revision:

1.0 --=-=-=-----

Title: Develop and get Approval for a Temporary Note Approvals:

Signature I Printed Name Developed By David Huff 02/03/2014 Validated By Facility Reviewer '.S Approximate Duration:

30 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

_________

_ Date: JPM RO C0-2 Page 1 of 15 NRC March 2014 CENG, " IO"""u'e ot I 0 t.!::eoF NINE MILE POINT NUCLEAR STATION References

1. CNG-OP-1.01-1005, Temporary Notes, Temporary Labels, Operator Aids, and Permanent Labels JPM RO C0-2 Page 2 of 15 NRC March 2014 a )Oint venture 0 =:natfon NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operators ability to develop and get approval for a Temporary Note. 2. Task Information:

a. NS-OM502-00004, Install and Use Authorized Labels. b. 2.1.15 (2. 7) Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, operations memos, etc. 3. Evaluation I Task Criteria Evaluation Method Perform Evaluation Location Classroom Time Critical Task No Alternate Path No LOD >1.0 Yes 4. Recommended Start Location a. Training Classroom

5. JPM Setup (if required)

a. Ensure book carts are available for the operators to use and that there is an up to date copy of CNG-OP-1.01-1005 available.

JPM RO C0-2 Page 3 of 15 NRC March 2014 a JO'""entuce of I

-:_*,eoF NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM RO C0-2 Page 4 of 15 NRC March 2014 CENGW aJOI'l: venture ol 0 =:'latJon

-;:,eoF I NINE MILE POINT NUCLEAR STATION INITIAL CONDMONS INITIATING CUE START TIME JPM RO C0-2 Given:

The plant is at 100% power.

The crew has recently discovered that 2SWP*TIK35A, CONTROL ROOM CHILLER 2HVK*CHL1A SVCE WTR OUTLET TEMP controller is difficult to place in MANUAL CONTROL.

Specifically, when shifting the controller from AUTO to MANUAL, the operators have to hold the MAN pushbutton down for 2 to 3 seconds to get the controller to shift into MANUAL.

I&C has been contacted and have setup a repair schedule.

The controller is scheduled to be repaired in one week.

While waiting for repairs, I&C has said that the controller will still function and if it is necessary for the operators to shift the controller from AUTO to MAN, the operators will need to hold down the MAN pushbutton for 2 to 3 seconds.

The Control Room Supervisor has determined a Temporary Note is to be developed explaining this condition.

The controller is located on 2CEC*PNL870.

CR-2014-002568 is tracking the repair of the controller.

You are the operator assigned to develop the Temporary Note and get signature approval of the note through the Shift Manager. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Develop and get Shift Manager signature approval to post a Temporary Note for 2SWP*TIK35A per CNG-OP-1.01-1005, Section 5.2. Page 5 of 15 NRC March 2014 CENG .. a JOint venture of---, 0=:"--;;,eo* I NINE MILE POINT NUCLEAR STATION 1. 2. PERFORMANCE Provide repeat back of initiating cue Cue: Acknowledge repeat back providing correction if necessary.

Obtain a copy of the reference material and review I utilize the correct section of the procedure.

ACT. CODE P/5/NA p p Evaluators The remaining steps may be performed in any order. Note: EVALUATOR SAT I UNSAT STD: Proper communications used lAW CNG-OP-1.01-2001, Communications and Briefings.

SAT I UNSAT STD: Obtains a copy of OP-1.01-1005 and reviews section 5.2. The answer key attached to this JPM may be used to assist in the grading of the below steps. The operator may choose to use different words on the TEMPORARY

evaluators LABEL and TEMPORARY LABEL LOG than what is listed on the answer key. This is Note! acceptable as long as the intent of the TEMPORARY NOTE and LOG is consistent with the intent of the below steps. The Evaluator may use their judgment as to whether or not the intent of the below steps are met. Evaluators The operator may choose to fill out all portions of the Temporary Note and Log .NOte: prior to presenting the note to the SM for approval.

This is an acceptable action. 3. Using the provided blank Temporary Note, documents the following information:

A note stating that in order to place 2SWP*TIK35A in MANUAL, the MAN button must be depressed for 2 to 3 seconds. JPM RO C0-2 Page 6 of 15 p *PASS/ FAIL STD: On the provided Temporary Note, documents that in order to place 2SWP*Ttt<35A in MANUAL, the MAN pushbutton must be depressed fot 2 to 3 seconds. Or words to that effect. NRC March 2014 CENG .. a JO""tuce ot I 0 =:'latlon NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE EVALUATOR P/5/NA The SM authorization of the temporary note may be accomplished one of two . Ev.aJuators ways. The operator may write a SM name in the SM block on the temporary note and present it to the evaluator or the operator may leave the SM name blank and Note: allow the evaluator to write it in. Either method is acceptable provided the completed tag is presented to the SM for approval.

4. Presents the Temporary Note to the SM for p *PASS/ FAIL approval.

STD: Once at a minimum, the Cue: As the SM when presented with the note information is documented Temporary Note, if necessary, sign or on the provide!$

Temporary write your name on the block labeled Note, provides the Temporary "SM" and give it back to the operator.

Note to the SM for approval.

If the operator has already put a SM name in on the Temporary Note, just indicate your approval verbally to the operator and hand it back. 5. Documents the following additional data on p SAT/ UNSAT the temporary note: STD: On the provided The date Temporary Note, places today's

date. 6.

The Temporary Note Number p *PASS I FAIL STD: From the Temporary Notes Log., takes the next sequential number of 0-14-03. Documents this number on the provided Temporary Note. 7. Fills out the provided Attachment 1, p *PASS I FAIL Temporary Notes Log as follows: STD: Takes the next sequential

Temporary Note Number number of D-14-03. Documents this number on the provided Temporary Notes Log. JPM RO C0-2 Page 7 of 15 NRC March 2014 a J01'1l venture of---, o=latlon I NINE MILE POINT NUCLEAR STATION 8.

Date PERFORMANCE

9.

Requested By ACT. CODE EVALUATOR PIS INA p SAT I UNSAT STD: Documents today's date in the DATE block on the Temporary Notes Log. p SAT I UNSAT STD: The operator documents their name in the REQUESTED BY block on the Temporary Notes Log. Evaluators At a minimum, in the LOCATION block of the Temporary Notes Log, the operator must put P870. They may choose to add additional information such as Note: 2SWP*TIK35A, however it is not required.

10.

Location p *PASS I FAIL STD: Documents the temporary note location of P870 in the LOCATION block of the provided Temporary Notes Log. 11.

Content of Temporary Note p *PASS I FAIL STD: Documents the content of the temporary note in the CONTENT OF TEMPORARY NOTE block of the provided Temporary Notes Log. The wording the operator uses does not have to match exactly with that on the Temporary Note. The operator may choose to paraphrase, JPM RO C0-2 Page 8 of 15 NRC March 2014 o JO<Ot vectuce ol I NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE EVALUATOR PI 5 INA 12.

Comments p SAT/ UNSAT STD: Places the Condition Report Number CR-2014-002568 in the COMMENTS block of the TEMPORARY NOTES LOG. 13.

Shift Manager Approval Signature p *PASS I FAIL Cue: As the SM, when presented with the STD: Presents the completed Attachment 1, sign in the block labeled TEMPORARY NOTES LOG to the "Shift Manager Approval Signature".

Shift Manager for approval.

Unless the operator would like to perform an additional review of all the Evaluators paperwork, then when the operator requests the SM sign the Temporary Notes Note: Log, inform the operator that another operator will perform the action of attaching the Temporary Note to the panel and their task is complete.

TERMINATING CUE The Operator has presented the completed Temporary Notes Log and Temporary Note to the SM for review and approval.

STOPnME JPM RO C0-2 Page 9 of 15 NRC March 2014 aJOI'lt venture NINE MILE POINT NUCLEAR STATION JPM RO C0-2 Evaluator's Answer Key Do Not Provide to Candidate CR TEMP NOTE No. 0-14-03 Date Today's Date SM Eval. Sign Here When placing 2SWP*TIK35A in MANUAL control, hold in the MAN pushbutton for 2 to 3 seconds. Page 10 of 15 NRC March 2014 CENGW a J0'""ectuce of I 0 =:--ion NINE MILE POINT NUCLEAR STATION Temporary Note Number 0-13-036 0-13-037 0-13-038 0-14-01 0-14-02 0-14-03 Date 09/17/13 11/10/13 12/15/13 01/12/14 02/20/14 Today's Date Requested By (Please Print) Toothaker Tanguay Hoskins Andrus Wilcox Operators Name JPM RO C0-2 Evaluator's Answer Key Do Not Provide to Candidate Attachment 1, Temporary Notes Log Location Content of Temporary Note Shift Manager Approval Signature P632, Printer turned off due to excessive paper I 2MSS*TRSH 1002 ---use. P851 Pump in PTL, auto starts when placed in /L--2TML-P4 standby P873 Div. 1 H202 2CMS*PNL66A Inop when lined up to /\------.__

Sample Path Suppression Pool Selector Switch P623 Amps less than required.

Below minimum 2MSS*AOV7D amperage P851 Dual Indication. 2MSS-PV28A When placing 2SWP*TIK35A in MANUAL, P870 depress the MAN pushbutton for 2 to 3 Evaluator, Sign Here seconds. -------------------Comments (1) CR-2013-006789 CR-2013-007724 CR-2013-008645 CR-2014-001104 CR-2014-002193 CR-2014-002568 Page 11 of 15 NRC March 2014 Shift Manager Removal Signature and Date Toll tojo5jtJ :Marft qreer 12/30/13 a JOrnt venture of ,

-;:,eOF ! NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INinATING CUE JPM RO C0-2 JPM Handout Given:

The plant is at 100% power.

The crew has recently discovered that 2SWP*TIK35A, CONTROL ROOM CHILLER 2HVK*CHL1A SVCE WTR OUTLET TEMP controller is difficult to place in MANUAL CONTROL.

Specifically, when shifting the controller from AUTO to MANUAL, the operators have to hold the MAN pushbutton down for 2 to 3 seconds to get the controller to shift into MANUAL.

I&C has been contacted and have setup a repair schedule.

The controller is scheduled to be repaired in one week.

While waiting for repairs, I&C has said that the controller will still function and if it is necessary for the operators to shift the controller from AUTO to MAN, the operators will need to hold down the MAN pushbutton for 2 to 3 seconds.

The Control Room Supervisor has determined a Temporary Note is to be developed explaining this condition.

The controller is located on 2CEC*PNL870.

CR-2014-002568 is tracking the repair of the controller.

You are the operator assigned to develop the Temporary Note and get signature approval of the note through the Shift Manager. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Develop and get Shift Manager signature approval to post a Temporary Note for 2SWP*TIK35A per CNG-OP-1.01-1005, Section 5.2. Page 12 of 15 NRC March 2014 a JOint venture of---, o=:llatfon i NINE MILE POINT NUCLEAR STATION JPM RO C0-2 CONTROL BLDG CHILLER HVK .. CHL1A *' ' DIV I CHILLER COMPRESSOR AUX OIL PUMP Page 13 of 15 CONTROL ROOM CHILLER HVK .. CHL1A SVCE VVTR OUTLET TEMP 2SWP""TIK35A NRC March 2014 aJOI'It venture of I o=: .. Hon NINE MILE POINT NUCLEAR STATION JPM RO C0-2 CR TEMP NOTE No. Date SM Page 14 of 15 NRC March 2014 CENGW a JO'" 'entuce ot I o=:uation NINE MILE POINT NUCLEAR STATION Temporary Note Number 0-13-036 0-13-037 0-13-038 0-14-01 0-14-02 Date 09/17/13 12/10/13 12/15/13 01/12/14 02/20/14 Requested By Location (Please Print) Toothaker P632, 2MSS*TRSH1002 Tanguay P851 2TML-P4 P873 Hoskins Div. 1 H202 Sample Path Selector Switch Andrus P623 2MSS*AOV7D Wilcox P851 2MSS-PV28A Attachment 1, Temporary Notes Log Content of Temporary Note Shift Manager Comments Shift Manager Approval Signature (1) Removal Signature and Date Printer turned off due to excessive paper CR-2013-use. 006789 Pump in PTL, auto starts when placed in /'-------_, CR-2013-standby 007724 2CMS*PNL66A Inop when lined up to CR-2013-------. y-12/30/13 Suppression Pool 008645 Amps less than required.

Below minimum CR-2014-amperage 001104 Dual Indication.

}flz___--CR-2014-002193 . 1. During the quarterly review, initiate a Permanent Label Request for Notes exceeding a year with exception of Notes required due to an extended outage or equipment deficiency.

For Notes exceeding a year, annotate in the "Comments" block either "Label Requested", "WO # ",or "Extended Outage". JPM RO C0-2 Page 15 of 15 NRC March 2014 CENG.

MILE NUCLEAR Sl"f.;riON Training Id: 2013 NRC RO Admin EC Revision:

1.0 _ __:o_ __ _ Title: Defeat the Reactor Building Ventilation LOCA Isolation Signals Approvals:

Signature I Printed Name Developed By David Huff 02/03/2014 Validated By 'i /1.e1'1 Facility Reviewer *_s Approximate Duration:

45 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

Date: JPM RO EC Page 1 of 18 NRC March 2014 CENG." a JOI'lt venture of I NINE MILE POINT NUCLEAR STATION References

1. N2-EOP-6.26, Defeating Reactor Building Ventilation LOCA Isolation Signals JPM RO EC Page 2 of 18 NRC March 2014 CENG .. DJOI'll venture oi I 0

... *-eoF I -'" NINE MILE POINT NUCLEAR STI\r!ON Instructor Information A. JPM Information

1. Description

a. This JPM tests the operators ability to describe how the Reactor Building Ventilation LOCA Isolation Signals are defeated.

2. Task Information:

a. N2-EOP06-01001-26, Implement N2-EOP-6.26, Defeat Reactor Building Ventilation LOCA Isolation Signals b. 2.2.41 (3.5) Ability to obtain and interpret station electrical and mechanical drawings 3. Evaluation 1 Task Criteria Evaluation Method Perform Evaluation Location Classroom Time Critical Task No Alternate Path No LOD >1.0 Yes 4. Recommended Start Location a. Training Classroom

5. JPM Setup (if required)

a. Print out enough copies of N2-EOP-6.26 for each operator to have one. JPM RO EC Page 3 of 18 NRC March 2014 ajOI<ll venture of l 0 NINE MILE POINT NUCLEAR STATION b. Ensure a copy of the following ESKs have been printed out for use by the operators.

Print out enough copies so that each operator may have a set. It is best to print out the ESKs on 11X17 sheets: 1) 07HVR01 through 12 (17 drawings in all) JPM RO EC Page 4 of 18 NRC March 2014 a]OI'lt venture ol I 0 .. lion -;:,eoF NINE MILE POINT NUCLEAR SlAriON B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM RO EC Page 5 of 18 NRC March 2014 a JOlf'*l venture of I 0 NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INITIATING CUE I STARTTIME Given:

The plant has experienced a LOCA and Secondary Containment high temperatures.

Drywell pressure is 10 psig and RPV Water level is 5 inches.

The EOP Director has directed performance of N2-EOP-6.26, Defeating Reactor Building Ventilation LOCA Isolation Signals.

You are the operator assigned to perform N2-EOP-6.26.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Complete the attached worksheet regarding Defeating the Reactor Building Ventilation LOCA Isolation Signals. PERFORMANCE ACT. CODE EVALUATOR PIS INA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used lAW CNG-OP-1.01-2001, Communications and Briefings.

2. Obtain a copy of the reference material and p SAT I UNSAT review I utilize the correct section of the procedure.

STD: Obtains copies of N2-EOP-6.26 and HVR ESKs :, Evaluators The following steps may be performed in any order. Note: Evaluators The Answer Key attached to this JPM can be used to assist in grading of the Note: below steps. JPM RO EC Page 6 of 18 NRC March 2014 a JOI'It venture ol l NINE MILE POINT NUCLEAR STATION Evaluators Note: Evaluators Note: PERFORMANCE ACT. CODE PIS INA EVALUATOR Due to the nature of this type of JPM, the answers given on the worksheet by the operator may not match exactly what is on the provided answer key. This is acceptable as long as the intent is met as determined by the Evaluator.

If there is a question by Evaluator as to the intent of what information the operator is attempting to provide, the Evaluator may verbally question the operator to ascertain the intent. When grading the below steps, the Evaluator should take into account any information gained through verbal discussion with the operator.

The operator may include additional components not listed on the answer key that may be affected by the LOCA isolation signal. This is acceptable.

1. Determine which conditions will cause the Reactor Building Ventilation System to isolate. p *PASS/ FAIL STD: Documents the following information in Block l of the provided Worksheet:

2. Determine which Division 1 air operated dampers (AODs) in the Reactor Building Ventilation System are directly affected by a HVR system isolation.

JPM RO EC Page 7 of 18 p

Above Refuel Roor High Radiation and/or RE14A or Bin ALARM.

Below Refuel Floor High Radiation and/or RE32A or Bin ALARM.

RB Ventilation System Low Flow Condition (or similar)

LOCA Signal (High DW Pressure or Low RPV Water Level *PASS I FAIL STD: Documents the following information in Block 2 of the provided Worksheet:

2HVR*AOD1A

2HVR*AOD9A

2HVR*AOD10A The operator may also include noun name descriptions for the components.

NRC March 2014 CENG" o IM veotuce ot J NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE PIS INA EVALUATOR Evaluators Note: At the completion of Questions 1 and 2, the operator will turn in their worksheet.

When the operator turns in their completed worksheet, hand them the worksheet with Questions 3 and 4 on it. Evaluators Note: Step 3 below should be graded by both reviewing the information the operator documented in Block 3 as well as a verbal discussion between the Evaluator and operator as to how the LOCA isolation is defeated for AOD1A. 3. 4. Describe how the Division 1 LOCA Isolation is defeated for 2HVR*AOD1A Determines what will happen to the Reactor Building Ventilation System if an Above Refuel Floor Radiation Monitor RE14A and B experience a high radiation condition above their ALARM setpoint when the LOCA signal isolation is defeated.

p *PASS I FAIL STD: Documents in Block 3 how the Division 1 RB Ventilation LOCA signal is defeated for AOD1A. If necessary, provides a verbal description to the Evaluator of how the isolation is defeated.

Key information needed:

ESK Location of the contact where Lead R4 is lifted

Description of the affected relay 3-2-* How AOD1A, is prevented from dosing on a LOCA signal by explaining the solenoids and Contact Ml to Rl. *PASS I FAIL STD: On the provided worksheet in Block 4, cirdes ISOLATE TERMINATING CUE The Operator has completed the JPM worksheet and returned it to the Evaluator.

The Evaluator has discussed any unclear information contained on the worksheet JPM RO EC Page 8 of 18 NRC March 2014 CENG. NINE MILE POINT NUCLEAR STATION STOP TIME JPM RO EC Page 9 of 18 NRC March 2014

a JOint venture oi--l NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate List ALL the conditions which would cause a running Reactor Building Ventilation

1. system to isolate (setpoints are not required, just a description of the isolation signals):

2.

Above Refuel Floor High Radiation I RE14A or B in Alarm

Below Refuel Floor High Radiation I RE32A or B in Alarm

RB Ventilation Low Flow Condition

LOCA Signal -or-High Drywell Pressure I Low RPV Level The operator may choose to add additional isolation signals. That is acceptable provided at least the above information is provided.

Which Division 1 air operated dampers (AODs) in the Reactor Building Ventilation System are directly affected by a HVR System isolation signal?

2HVR*AOD1A

2HVR*AOD9A

2HVR*AOD10A When you have answered Questions 1 and 2, turn in your completed worksheet to the Evaluator.

JPM RO EC Page 10 of 18 NRC March 2014 CENGW a )Otf"t venture of I O=:'laHon NINE MILE POINT NUCLEAR STATION 3. Evaluator's Answer Key Do Not Provide to Candidate Using the provided Reactor Building Ventilation Drawings, describe how N2-EOP-6.26, Step 6.1.1 is used to prevent 2HVR*AOD1A from isolating on a LOCA Signal. Explain all leads lifted, relays, solenoids, and contacts which are affected.

Document as much information as possible in the space below. Additionally at the end of this lPM, you will be given the opportunity to verbally explain to the Evaluator how the isolation is defeated.

N2-EOP-6.23, Step 6.1.1 requires the operator to lift the lead on Contact 4 of relay 2A-10-2ISCA02 in 2CEC*PNL859.

The contact from which the lead is lifted can be found on ESK 07HVR10 Sheet 1 on the upper left hand side of the drawing.

When the lead (R4) is lifted, it prevents Relay 3-2-from energizing when a LOCA signal is present:

If energized, Relay 3-*2-would send a signal to Contact M1 to R1 to OPEN .

Contact M 1 to R1 can be found on ESK 07HVR06, Sheet 1 on the left hand side. This contact is associated with AOD1A.

AOD1A will close if its associated solenoid valves deenergize, so preventing the solenoids from deenergizing would prevent the AOD from closing.

If Contact M1 to R1 OPENS, it will cause the AOD1A solenoids to deenergize.

By preventing a LOCA signal from opening the M 1 to R1 contact, it prevents the AOD1A solenoids from deenergizing thus preventing AOD1A from closing. JPM RO EC Page 11 of 18 NRC March 2014 CENG," aJOI'llventureof---

0 =:'l.tlon NINE MILE POINT NUCLEAR STAfiON Evaluator's Answer Key Do Not Provide to Candidate Division 1 LOCA isolation Signal from ESK 07HVR10, Sheet 1: JPM RO EC P85'9 GPI ,OJ t..l Lift Lead R4 from Here I(P/ £ .

J<V,.JI.,./1

(/ICT£"2.)

_. Relay 3-2-is prevented from energizing on a LOCA Signal Page 12 of 18 NRC March 2014 a)OI'1tventureof--

O=-otlon -;:,_eoF I NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate 2HVR*AOD1A from ESK 07HVR06, Sheet 1 (AOD9A and lOA are similar):

JPM RO EC L, ___ .StJPPL)'

l ISOL/9770N ZJIV./2,JfJfJtJOII9

.. *r .em Ill 74-1-84-fiPJ )({H) j(){) Contact Ml to Rl is prevented from opening. If it can't open, it cannot shut the AOD on a LOCA signal . 311 0! Page 13 of 18 NRC March 2014 CENG." a ]Oint venture of--NINE MILE POINT NUCLEAR STAriON Evaluator's Answer Key Do Not Provide to Candidate

4. Once the actions of N2-EOP-6.26 have been performed and Reactor Building Ventilation has been restarted, what would happen to the system if the Above Refuel Floor Radiation Monitors RE14A and B experienced radiation levels above their ALARM setpoint?

{circle one) Continue to Run Isolate JPM RO EC Page 14 of 18 NRC March 2014 a JOI'lf venture of I NINE MILE POINT NUCLEAR STATION 3. Using the provided Reactor Building Ventilation Drawings, describe how N2*EOP* 6.26, Step 6.1.1 is used to prevent 2HVR*AOD1A from isolating on a LOCA Signal. Explain all leads lifted, relays, solenoids, and contacts which are affected.

Document as much information as possible in the space below. Additionally at the end of this lPM, you will be given the opportunity to verbally explain to the Evaluator how the isolation is defeated.

JPM RO EC Page 15 of 18 NRC March 2014 a )01'1! venture of I O=:H.r:lon

'!::eoF NINE MILE POINT NUCLEAR STATION 4. Once the actions of N2-EOP-6.26 have been performed and Reactor Building Ventilation has been restarted, what would happen to the system if th<<S Above Refuel Floor Radiation Monitors RE14A and B experienced radiation levels above their ALARM setpoint? (circle one) Continue to Run Isolate JPM RO EC Page 16 of 18 NRC March 2014 CENG .. <J.)Ointventureof I

NINE MILE POINT NUCLEAR SlATION INITIAL CONDITIONS INI.TlATlNG CUE JPM RO EC JPM Handout Given:

The plant has experienced a LOCA and Secondary Containment high temperatures.

Drywell pressure is 10 psig and RPV Water level is 5 inches.

The EOP Director has directed performance of N2-EOP-6.26, Defeating Reactor Building Ventilation LOCA Isolation Signals.

You are the operator assigned to perform N2-EOP-6.26.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Complete the attached worksheet regarding Defeating the Reactor Building Ventilation LOCA Isolation Signals. Page 17 of 18 NRC March 2014 CENG .. " a JOint ventureof--

NINE MILE POINT NUCLEAR STATION 1. 2. JPM Worksheet List ALL the conditions which would cause a running Reactor Building Ventilation system to isolate (setpoints are not required, just a description of the isolation signals):

Which Division 1 air operated dampers (AODs) in the Reactor Building Ventilation System are directly affected by a HVR System isolation signal? When you have answered Questions 1 and 2, turn in your completed worksheet to the Evaluator.

JPM RO EC Page 18 of 18 NRC March 2014 0--,..,l'r,..eoF!

_;__ __ """' i NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC RO Admin EP Revision:

0.0 ----=....;;...;;;_

__ _ Title: Fire Fighting Response for a Fire in the Protected Area Approvals:

Signature I Printed Name Developed By 12/18/2013 Validated By Doug Mizener 12/13/2013 Facility Reviewer Aaron Armstrong I 13 JUJI'f ,. ' Approximate Duration:

Documentation of Performance:

Performer:

Evaluator:

Start Time: Grade: Comments:

Stop Time: Pass I Fail 15 minutes Completion Time Evaluators Signature:

_________

_ Date: JPM RO EP Page 1 of 13 NRC March 2014 a JOint venture of-=::l O=:n.tlon NINE MILE POINT NUCLEAR STATION References

1. EPIP-EPP-28, Firefighting

2. EPIP-EPP-OSA, Local Area/Building Evacuation JPM RO EP Page 2 of 13 NRC March 2014 CENGW NINE MILE POINT NUCLEAR STATION Instructor Information A. l PM Information

1. Description

a. This JPM tests the operators ability to perform the RO actions for a fire in the protected area. 2. Task Information:

a. N2-285001-01001, Utilize Interplant Communications Subsystems.

b. 2.4.39 (3.9) Knowledge of RO responsibilities in emergency plan implementation

3. Evaluation I Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical Task No Alternate Path No LOD >1.0 Yes 4. Recommended Start Location a. Unit 2 Simulator

5. JPM Setup (if required)

a. Ensure book carts are available for the operators to use and that there is an up to date copy of EPIP-EPP-28.

Print out enough copies of Attachment 1 so that each operator gets a copy. JPM RO EP Page 3 of 13 NRC March 2014 a jOint venture of-:=l NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM RO EP Page 4 of 13 NRC March 2014 UJOinl venture of-=-:=-1 O=:'*atlon NINE MILE POINT NUCLEAR STATION Given: INITIAL CONDinONS

You are the on-shift Control Room Operator (CRO).

The SM has been notified of a confirmed fire in the Unit 2 Turbine Building, 250' Elevation Truck Aisle.

This area is not a C02 or Halon Protected Area.

The OSC has not been activated.

This is a drill Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions INITIATING CUE (Operators Name), Perform the CRO actions for the fire per EPIP-EPP-28, Attachment 1 I STARTTIME PERFORMANCE ACT. CODE EVALUATOR P/5/NA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used lAW CNG-OP-1.01-2001, Communications and Briefings.

2. Obtain a copy of the reference material and p SAT I UNSAT review I utilize the correct section of the procedure.

STD: Obtains a copy of EPIP-EPP-28 and reviews Attachment

1. 3. Upon notification of a fire, or upon receipt of p *PASS I FAIL an alarm AND actuation of an automatic Fire Suppression System: STD: On the GAITRONICS, places tbe MERGE switch in MERGE.

RED a. Place the GAitronics system in the Merge MERGE light is lit. Mode JPM RO EP Page 5 of 13 NRC March 2014 a JOint venture of-:-=::-1 NINE MILE POINT NUCLEAR STATION PERFORMANCE

4. b. If the event is a drill, make the following announcement preceding the fire alarm: "This is a drill, this is a drill." 5. c. Sound the Fire Alarm for 10 seconds. 6. Make the following announcement: "Attention, Attention, this is (an actual event) (a drill). A fire has been detected at Unit{1/2) in the (state building location, elevation, if known). The Nine Mile Point Fire Brigade shall report to the Unit {1/2) assembly area or (other location as directed by the Fire Brigade Leader). All other personnel are to remain clear of the (state building location, elevation)." Cue: If asked, the FBL does not want a different assembly area. 7. Repeats the alarm and announcement.

Cue: The alarm and announcement have been repeated.

JPM RO EP Page 6 of 13 ACT. CODE EVALUATOR P/5/NA p SAT I UNSAT STD: Announces into the HANDSET "This is a drill, This is a drill" while holding down the talk pushbutton or INST Switch. p *PASS/FAIL STD: On the. GA/TRONICS, to sound the alarm for approximately 10 .seconds.

p *PASS/FAIL STD: Makes the. following annount;ement on into the Handset (or $lmilar) while holding down the talk pushbutton or INST Switch: Attention, Attention, this is a drill. A tire has been detected at Unit 2 in the Unit 2 Turbine Building Truck Aisle. The NMP Fire Briga$ shall report to the Unit 2 assembly area. All other personnel are to remain clear of the Unit 2 Turbine Building 250' Truck Aisle. p SAT I UNSAT STD: Repeats steps 4 through 6 NRC March 2014 CENG. a jOint venture of-=:l o=:ll .. lon NINE MILE POINT NUCLEAR STATION PERFORMANCE

8. d. IF the location of the alarm is a C02 protected fire zone, state this announcement following the message above: "This is a C02 protected area. All personnel shall immediately evacuate the (state building, location, and elevation) and all areas adjacent to and below this location." 9. e. Take the GAitronics system out of the Merge Mode, unless OSC has been activated

10. f. If the Fire Brigade Leader does NOT respond within 60 seconds, repeat Steps 1a-1c Cue: Inform the operator the Fire Brigade Leader has responded.

11. g. Notify the SM if the fire is confirmed JPM RO EP Page 7 of 13 ACT. CODE EVALUATOR PIS INA p SAT I UNSAT STD: Per the turnover determines the area is not C02 protected and determines this step is not applicable.

p SAT I UNSAT STD: Per the turnover determines the OSC is not activated.

On the GAITRONICS, pushes UP on the MERGE switch. Observes the RED MERGE light is not lit. Pushes DOWN on the OUTDOOR SPEAKERS and ADM ISOLATE switches to reactivate those speakers.

p SAT I UNSAT STD: Determines the FBL responded and this step is not applicable.

p SAT I UNSAT STD: Determines the SM has already been notified per the turnover.

NRC March 2014 CENG .. a JOI'lt venture of--:::=-1 NINE MILE POINT NUCLEAR STATION PERFORMANCE

12. Turn up volume on station radio base console, including Oswego County fire frequency

13. If this is a confirmed fire and it is outside the protected area, then request off-site fire assistance.

Call Oswego County 911Center (343-1313) and request off-site fire assistance

14. If requested by Fire Brigade Leader, then call Oswego County 911 Center (343-1313) and request off-site fire assistance Cue: As the FBL, inform the operator that off-site fire assistance is not required.

15. If off-site assistance is requested, then inform the Security Central Alarm Station (X2872) that off-site fire assistance has been requested

16. If required, initiate any Special Operating Procedures OR Emergency Operating Procedures Cue: As the SM/CRS, inform the operator that all applicable SOPs/EOPs have been entered and actions are being carried out JPM RO EP Page 8 of 13 ACT. CODE EVALUATOR P/5/NA p SAT I UNSAT STD: On the station radio base console, Turns up the volume including the one labeled "Oswego County Fire Control" p SAT I UNSAT STD: Per the turnover, the fire is not outside the protected area and determines this step is NA p SAT I UNSAT STD: Per the cue, determines this step is NA p SAT I UNSAT STD: Determines off-site assistance was not required and determines this step is NA p SAT I UNSAT STD: Per the cue determines all applicable SOPs/EOPs have already been entered. NRC March 2014 NINE MILE POINT NUCLEAR STATION PERFORMANCE

17. If a discharge of Halon or C02 occurs, reference EPIP-EPP-11, Hazardous Material Incident Response, N1-0P-21C, Fire Protection System -LP/HPC02, N1-0P-21D, Fire Protection System -Halon 1301, N2-0P-45, Fire Protection Carbon Dioxide, and N2-OP-46, Fire Protection

-Halon 18. Check Process Radiation Monitors to determine if there is any rise in effluent activity Cue: The radiation monitors do not show any rise in effluent activity 19. If SM implements a local area/building evacuation, then perform duties in EPIP-EPP-OSA Cue: As the SM, inform candidate the Turbine Building is to be evacuated and provide candidate with a prepared (last page of JPM) EPIP-EPP-5A, Attachment 1 Evacuation Form Place the GAitronics system in the Merge Mode 20. Sound the Evacuation Alarm for 10 seconds. JPM RO EP Page 9 of 13 ACT. CODE EVALUATOR PI 5 INA p SAT/ UNSAT STD: Per the turnover, determines this area is not protected by Halon or C02 p SAT I UNSAT STD: At the DRMS computer screen, observes radiation levels on the STACK. Determines per the cue that radiation monitors do not show any rise. p *PASS/ FAIL STD: On the GAITRONICS, places the MERGE switch in MERGE. Observes the RED MERGE light Is lit. p *PASS/ FAIL STD: On the GAITRONICS, places the EVACUATION ALARM switch to sound the alarm for approximately 10 seconds. NRC March 2014 NINE MILE POINT NUCLEAR STATION PERFORMANCE

21. Makes the evacuation announcement per the provided Evacuation Attachment.

Cue: As the Unit 1 SM, inform the operator to leave GAITRONICS in MERGE. Cue: When necessary, inform the operator the alarm and announcement have been repeated.

22. If fire is confirmed, then ensure the unaffected Unit SM is notified Cue: As the Unit 1 SM, inform the operator you have been informed.

JPM RO EP Page 10 of 13 ACT. CODE PI 5/ NA p EVALUATOR

PASS/ FAIL STD: Makes the following announcement into the Haru:lset (t;>r similar) while holding down the talk pushbutton or INST Switch: Attention, Attention, this is a drill. NMP0nit2is ordering an evacuation of the Unit 2 Turbine St.Jildlng due to a FIRE. All personnel are to leave the Unit 2 Turbine Building using the closes possible exist and report to RP ACCESS. Accountability is being performed, all personnel shall report to an assembly area, cared in and remain in the area until further notice. Personnel in protective clothing should leave the area immediately and obtain RP assistance at the conirol point. I repeat this is a drill. Repeats the alarm and announcement.

Leaves the GAITRONICS in MERGE. SAT I UNSAT STD: Contacts the Unit 1 SM and informs him of the Fire. NRC March 2014 a)ornt venture NINE MILE POINT NUCLEAR STATION PERFORMANCE

23. When notification is received that the fire is out and the event may be terminated, then perform the following Cue: As the FBL, inform the operator that the fire is out and the drill may be terminated.

24. a. Place GAitronics system in the Merge Mode 25. b. If the event is a drill, make the following announcement preceding the fire alarm: "This is a drill, this is a drill." c. Sound the Station Alarm for 10 seconds, and make the following announcement: "Attention, Attention, this is (an actual event) (a drill). The fire event is terminated." Repeat alarm and announcement Cue: The alarm and announcement have been repeated.

ACT. CODE EVALUATOR PIS/ NA p SAT I UNSAT STD: Acknowledges report from the FBL that the fire is out and the drill may be terminated p SAT I UNSAT STD: Determines GAITRONICS is already in MERGE by observing the RED MERGE light lit. p SAT I UNSAT STD: Makes the following announcement into the Handset (or similar) while holding down the talk pushbutton or INST Switch: This is a drill, this is a drill Sounds the station alarm for approximately 10 seconds. Attention, Attention, this is a drill. The fire event is terminated.

Repeats announcement TERMINATING CUE Both the CRO Firefighting checklist and Turbine Building evacuation have been performed.

STOP TIME JPM RO EP Page 11 of 13 NRC March 2014 a JO<et 'enture of I NINE MILE POINT NUCLEAR STATION Attachment 1, EMERGENCY ANNOUNCEMENT LOCAL AREA/BUILDING EVACUATION (No emergency classification has been declared)

Instructions: (check boxes to select appropriate announcement)

1. Place GAitronics in Merge, 2. Sound the EVACUATION alarm for 10 seconds 3. Announce (if checked, include in announcement), X a. Attention, Attention all personnel, This is X a drill o is an actual emergency X b. Nine Mile Point (Unit 1 £;}!is ordering an evacuation of the (Unit 1 f}j: (Provide specific location or building to TURBINE BUILDING X c. Due to: (provide conditions necessitating the evacuation)

__ -'-A-'-'F'-'1'-'-R'""'E,_

__ _ X d. All personnel are to leave the (Unit 1 TURBINE BUILDING (area/building).

o 1. Staying clear of ____________ (area/elevation) and reporlro ______________________

__ OR X 2. Using the closest possible exit, and reporl to RP ACCESS X e. Accountability is being performed; all personnel shall reporl to an assembly area, card in and remain in the area until furlher notice. X f. Personnel in protective clothing should (select appropriate):

o 1. Leave the area removing PC=s as indicated at the step off pad. OR X 2. Leave the area immediately and obtain Radiation Protection assistance at the control point. X g. I repeat, This is X a drill o is an actual emergency

4. Repeat the alarm and announcement.

5. Consult with opposite Unit's SM and determine if GAitronics should be left in Merge (required for declared emergencies) for the duration of the event. JPM RO EP Page 12 of 13 NRC March 2014 CENG, a JOint venture of-::=l NINE MILE POINT NUCLEAR INITIAL CONDITIONS INITIATING CUE JPM RO EP JPM Handout Given:

You are the on-shift Control Room Operator (CRO).

The SM has been notified of a confirmed fire in the Unit 2 Turbine Building, 250' Elevation Truck Aisle.

This area is not a C02 or Halon Protected Area.

The OSC has not been activated.

This is a drill Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Perform the CRO actions for the fire per EPIP-EPP-28, Attachment 1 Page 13 of 13 NRC March 2014 CENG. NINE MILE POINT NUCLEAR STAliON Training Id: 2013 NRC SRO Admin C0-1 Revision:

1.0 -----Title: Determine the Severity of a Reactivity Event and Actions Required Approvals:

Signature I Printed Name Developed By David Huff 02/14/2014 Validated By Carl Crawford 12/11/2013 Facility Reviewer Aaron Armstrong Approximate Duration:

20 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

_________

_ Date: JPM SRO CO-l Page 1 of 11 NRC March 2014 a JOIC"ectuce ot I 0 NINE MILE POINT NUCLEAR STATION References

1. N2-0P-96, Reactor Manual Control and Rod Position Indication System 2. CNG-OP-3.01-1000, Reactivity Management JPM SRO CO-l Page 2 of 11 NRC March 2014 NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operators ability to determine the actions necessary for a mispositioned control rod and provide a recommendation for the Reactivity Management Issue Severity Level. 2. Task Information:

a. CNG-OPS301-00006, Report Reactivity Management Incidents

b. K/A 2.1.37 (4.6) Knowledge of procedures, guidelines, or limitations associated with reactivity management.

3. Evaluation I Task Criteria Evaluation Method Perform Evaluation Location Classroom Time Critical Task No Alternate Path No LOD >1.0 Yes 4. Recommended Start Location a. Training Classroom

5. JPM Setup (if required)

a. Ensure book carts are available for the operators to use and that there is an up to date copy of N2-0P-96 and CNG-OP-3.01-1000 JPM SRO C0-1 Page 3 of 11 NRC March 2014 a JO>Ot "otuce ot 1 NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM SRO C0-1 Page 4 of 11 NRC March 2014 aj01'1t venture ol 0 =:ll*tlon I NINE MILE POINT NUCLEAR STATION INITIAL *** CONDITIONS INITIATING CUE START TIME Given:

The plant completed a rod pattern exchange at 72% power at 03:00 this morning.

At 03:15, reactor power was raised to 80%.

At 7:00, the crew determines control rod 02-43 was supposed to be withdrawn to position 42 per the RMI but was inadvertently withdrawn to position 44.

Rod 02-43 has been mispositioned for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 45 minutes.

No predictor case has been run with the Control Rod mispositioned.

You are the Control Room Supervisor (CRS) Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions

{Operators Name), Determine ALL required actions for this rod positioning.

Additionally, provide the recommended Reactivity Management Issue Severity Level for this event per CNG-OP-3.01-1000.

Document all communications and required actions on the provided worksheet.

PERFORMANCE ACT. CODE EVALUATOR P/S/NA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used JAW CNG-OP-1.01-2001, Communications and Briefings.

2. Obtain a copy of the reference material and p SAT I UNSAT review I utilize the correct section of the procedure.

STD: Obtains any of the following as necessary to determine the plant impact:

N2-0P-96

CNG-OP-3.01-1000 JPM SRO CO-l Page 5 of 11 NRC March 2014 a jOint venture oi i 0 Conetellation

-.*-eoF 1 E._.gy i NINE MILE POINT NUCLEAR STATION . NOte: PERFORMANCE ACT. CODE P/S/NA The following steps may be performed in any order . EVALUATOR E:waluators The Answer Key attached to this JPM may be used to assist in grading of the "+', ' Note: below steps. ., ' ' ,, Evaluators Note: When grading the below steps, the operator may choose to use different wording on the worksheet then what is on the answer key to represent the actions taken. This is acceptable, provided the intent and answer is obvious to the Evaluator.

If the Evaluator has a question as to what is documented on the worksheet, then the Evaluator may verbally question the operator to determine the intent. If the Evaluator verbally questions the operator as to what is documented, the answers the operator provides may be used to assist with the grading of the below steps.

Note: The operator may include additional actions not listed below on the provided worksheet.

This is acceptable but only the information in Steps 4 through 8 needs to be on the worksheet.

3. 4. Per N2-0P-96, performs the following actions:

Notify the SM Cue: If contacted as the SM, acknowledge the notification.

IF a Control Rod was found mispositioned when Control Rod movements were NOT being performed AND a periodic OR predictor case has NOT been run with the Control Rod(s) mispositioned AND Reactor power is above SO%, reduce Reactor power by 40 MWe. JPM SRO CO-l Page 6 of 11 s s SAT/ UNSAT STD: Determines per N2-0P-96 that the SM needs to be notified.

Documents the SM notification on the provided worksheet.

PASS l FAIL STD: Determines per N2-0P-96 and the turnover that rod moveml!nts. not being performed atthis.time.and a predictor case has not been run and power is abOve SOOfo. Determines power needs to be lowered by 40MWe. Documents.

the power reduction on the provided WQrksheet. . NRC March 2014 CENG, a]OH1t venture ol-----, o=--:,eDF I NINE MILE POINT NUCLEAR STATION PERFORMANCE

5.

Contact the following for instructions:

0 On-Call Reactor Engineer 0 General Supervisor Operations

-Unit 2 Cue: If contacted as the RE or GSO, acknowledge the notification and inform the operator you have no further direction at this time. 6.

Provide the Reactor Engineer with the following information about mispositioned Control Rod(s): 0 Location 0 Position 0 Duration 7.

Initiate a CR in accordance with CNG-CA-1.01-1000 to document the mispositioned Control Rod event regardless of the apparent cause. Cue: If necessary, inform the operator that a CR has been initiated.

8. Per CNG-OP-3.01-1000, Determines a recommended Reactivity Management Issue Severity Level ACT. CODE EVALUATOR PIS INA s *PASS I FAIL STD: Determines per N2-0P-96 that the RE and G$0 need to be contacted.

the need to notify the' RE and GSO on the provided worksheet.

s *PASS/ FAIL STD: Determines per N2-0P-96 that the RE needs to be told the following:

Rod Location

Rod Position (44)

Duration (2:45) Documents the informatic>n on the provided worksheet.

s *PASS I FAIL STD: Determlnes per N2-0P-96 that a CR needs to be initiated.

Documents the need for a CR on the provided worksheet.

s *PASS I FAIL STD: Determines per CNG-OP-3.01-1000, Attachment 1 that the recommended Reactivity management Issue Severity Level is LEVEL 2. Documents the SV. on the provided worksheet.

TERMINATING CUE The Operator has completed the JPM hand out and returned it to the Evaluator.

JPM SRO CO-l Page 7 of 11 NRC March 2014

0=: .... "'" -;:,eDF I NINE MILE POINT NUCLEAR STATION STOP TIME JPM SRO CO-l Page 8 of 11 NRC March 2014 CENG" aJOI'lt venture of l 0 =:'a.uon NINE MILE POINT NUCLEAR STATION 1. 2. Evaluator's Answer Key Do Not Provide to Candidate Required Actions and Communications for Mispositioned Control Rod (list ALL required communications and actions):

Notify the Shift Manager

Reduce Power by 40 MWe

Contact Reactor Engineer (RE) and General Supervisor Operations

Provide the RE with the mispositioned rod Location, Position, and Duration (Rod 02-43, At position 44, Been mispositioned for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 45 minutes).

Initiate a Condition Report (CR) -i . _. The Recommended Reactivity Management Issue Severity Level for this event per CNG-OP-3.01-1000:

Severity Level 2 JPM SRO CO-l Page 9 of 11 NRC March 2014 a JOI'l! venture of O=:Rmion -;:,eOF I NINE MILE POINT NUCLEAR STATION INITIAL INITIAnNG CUE JPM SRO CO-l JPM Handout Given:

The plant completed a rod pattern exchange at 72% power at 03:00 this morning.

At 03:15, reactor power was raised to 80%.

At 7:00, the crew determines control rod 02-43 was supposed to be withdrawn to position 42 per the RMI but was inadvertently withdrawn to position 44.

Rod 02-43 has been mispositioned for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 45 minutes.

No predictor case has been run with the Control Rod mispositioned.

You are the Control Room Supervisor (CRS) Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Determine ALL required actions for this rod positioning.

Additionally, provide the recommended Reactivity Management Issue Severity Level for this event per CNG-OP-3.01-1000.

Document all communications and required actions on the provided worksheet.

Page 10 of 11 NRC March 2014 a JOI'lt venture oi I 0 =:' .. Hon NINE MILE POINT NUCLEAR STATION JPM Worksheet

1. Required Actions and Communications for Mispositioned Control Rod (list ALL required communications and actions):

2. The Recommended Reactivity Management Issue Severity Level for this event per CNG-OP-3.01-1000:

JPM SRO CO-l Page 11 of 11 NRC March 2014 CENG_

i NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC SRO Admin C0-2 Revision:

0.0 Title

Determine Plant Impact for Inoperable Unit Cooler Approvals:

Signature I Printed Name Developed By David Huff 12/18/2013 Validated By Carl Crawford 12/11/2013 Facility Reviewer Aaron Armstrong Approximate Duration:

__

Documentation of Performance:

Performer:

Evaluator:

Start Time*: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

_________

_ Date: JPM SRO C0-2 Page 1 of 10 NRC March 2014 CENGW a JOrr>t venture of---, o=* ... *-

I NINE MILE POINT NUCLEAR STATION References

1. N2-0P-53E, Standby Switchgear/Battery Room Ventilation System 2. NMP Unit 2 Technical Specifications JPM SRO C0-2 Page 2 of 10 NRC March 2014 CENG.N BJOI'1tventuceoi--J o=:natlon NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operators ability to determine the plant impact of an inoperable unit cooler. 2. Task Information:

a. NS-PSllS-02003, Initiate Action to Comply With Technical Specifications

b. K/ A 2.1.32 ( 4.0) Ability to explain and apply system limits and precautions.

3. Evaluation I Task Criteria Evaluation Method Perform Evaluation Location Classroom Time Critical Task No Alternate Path No LOD >1.0 Yes 4. Recommended Start Location a. Training Classroom

5. JPM Setup (if required)

a. Ensure book carts are available for the operators to use and that there is an up to date copy of N2-0P-53E and Unit 2 Technical Specifications.

JPM SRO C0-2 Page 3 of 10 NRC March 2014 NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM SRO C0-2 Page 4 of 10 NRC March 2014 a IOI'lt venture oi I NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INMAnNG CUE START TIME Given:

The plant is operating at 100% power.

While taking building rounds, an operator notices the Division 1 Chiller Equipment Room is warmer than normal.

Upon investigation, operators found 2SWP*V221A, HVC*UC103A INLET ISOL valve shut.

All attempts to re-open 2SWP*V221A have failed. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Determine the impact of this valve failure on plant operations.

Document your results on the provided worksheet.

PERFORMANCE ACT. CODE EVALUATOR PI 5 INA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used lAW CNG-OP-1.01-2001, Communications and Briefings.

2. Obtain a copy of the reference material and p SAT I UNSAT review I utilize the correct section of the procedure.

STD: Obtains any of the following as necessary to determine the plant impact:

N2-0P-53E

PID 53E

PID 111

Unit 2 Technical Specifications

' ',,:.,' ,:':*::*.

'

The following steps may be performed in any order . .

JPM SRO C0-2 Page 5 of 10 NRC March 2014 CENG_ NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE PIS/ NA EVALUATOR

dttom/

The operator may choose to use different nomenclature to represent the affected component.

This is acceptable provided it is obvious to the evaluator which component is affected.

The Evaluators Aid at the end of this JPM may be used to assist in the grading of the below steps. The listing of the references on the Evaluators Aid is for ease of grading and review by the Evaluator, however it is not required for successful completion of the JPM. 3. 4. 5. Determines the following:

The closure of 2SWP*V221A makes 2HVC*UC103A inoperable

With 2HVC*UC103A inoperable, 2HVK*CHL1A is inoperable

Determines TS 3.7.3 Conditions A and B are applicable.

JPM SRO C0-2 Page 6 of 10 p p p *PASS I FAIL STD: On the provided worksheet, documents that 2HVC*UC103A'I*DN1SION 1 CHILLER ROOM UNITSPACE COOLER is INOPERABLE

PASS/ FAIL STD: On .the provided documents that 2HVK*CHL1A, DIVISION 1 CONTROL AND REI.AY ROOM CHILLER is INOPERABLE

PASS I FAIL STD: References TS 3.7.3, Conditions A and B and documents the following as a minimum on the provided worksheet:

Restore .the Division 1 Control Room Envelope AC Subsystem for the Main Control Room to OPERABLE status. Within 30 days

Restore the Division 1 Control Room Envelope AC Subsystem for the Relay Room to OPERABLE status within 30 days NRC March 2014 a JOint venture of----, 0 =,.....,

I NINE MILE POINT NUCLEAR STATION TERMINAnNG CUE I STOPTIME JPM SRO C0-2 The Operator has completed the JPM hand out and returned it to the Evaluator.

Page 7 of 10 NRC March 2014 a po.,eotu'e ot I 0 NINE MILE POINT NUCLEAR STATION 1. 2. 3. Evaluator's Answer Key Do Not Provide to Candidate Status of 2HVC*UC103A:

INOPERABLE List any other impacted equipment and its status: 2HVK*CHL1A, DIVISION 1 CONTROL AND RELAY ROOM CHILLER is INOPERABLE

' List actions required to be performed (include reference document and section).

Enter TS 3. 7 .3, Conditions A and B. (N2-0P-53E, Attachment 1, Action 4) Condition A: Restore Division 1 control room envelope AC subsystem for the Main Control Room area to OPERABLE status within 30 days. Condition B: Restore Division 1 control room envelope AC subsystem for the Relay Room area to OPERABLE status within 30 days. JPM SRO C0-2 Page 8 of 10 NRC March 2014 a )01'11 venture of I NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INITIATING CUE. JPM SRO C0-2 JPM Handout Given:

The plant is operating at 100% power.

While taking building rounds, an operator notices the Division 1 Chiller Equipment Room is warmer than normal.

Upon investigation, operators found 2SWP*V221A, HVC*UC103A INLET ISOL valve shut.

All attempts to re-open 2SWP*V221A have failed. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Determine the impact of this valve failure on plant operations.

Document your results on the provided worksheet.

Page 9 of 10 NRC March 2014 a JOint venture ol --------, o=llatiM I NINE MILE POINT NUCLEAR STATION JPM Worksheet

1. Status of 2HVC*UC103A:

lr 2. List any other impacted equipment and its status: .. 3. List actions required to be performed (include reference document and section).

' JPM SRO C0-2 Page 10 of 10 NRC March 2014 CENG_ NINE MILE POINT NUCLEAR STA110N Training Id: 2013 NRC SRO Admin EC Revision:

0.0 -----'-----

Title: Determine Components Which Need Protection Approvals:

Signature I Printed Name Developed By David Huff 12/18/2013 Validated By Tom Tanguay 12/18/2013 Facility Reviewer Aaron Armstrong Approximate Duration :

__ Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

_________

_ Date: JPM SRO EC Page 1 of 15 NRC March 2014 a)otnt ventureof--

o=Hatlon -:,eDF I NINE MILE POINT NUCLEAR STATION References

1. S-ODP-OPS-0122, NMP Site Specific Equipment Protection Matrices 2. CNG-0P-GL012, Equipment Protection Guideline JPM SRO EC Page 2 of 15 NRC March 2014 CENG., a JO'c"ectu*e ot I 0 NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operators ability to evaluate plant conditions and determine which components need to be protected.

2. Task Information:

a. NS-FLDSUP-013, Protect Plant Equipment.

b. K/A 2.2.14 (4.3) Knowledge of the process for controlling equipment configuration or status. 3. Evaluation I Task Criteria Evaluation Method Perform Evaluation Location Classroom Time Critical Task No AJternate Path No LOD >1.0 Yes 4. Recommended Start Location a. Training Classroom

5. JPM Setup (if required)

a. Ensure book carts are available for the operators to use and that there is an up to date copy of S-ODP-OPS-0122 and CNG-0P-1.01-GL012.

b. Ensure a copy of the electrical print stick EE-001 series is available for the operators to review. JPM SRO EC Page 3 of 15 NRC March 2014 a IO""entuce of I NINE MILE POINT NUCLEAR STATION c. If multiple operators are going to perform the JPM at the same time, ensure each operator has a copy of 5-0DP-OPS-0122 and GL012. JPM SRO EC Page 4 of 15 NRC March 2014 CENG,. ' JO>e! vec!uce ol I NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM SRO EC Page 5 of 15 NRC March 2014 a JO"t "otuce ot I 0 =:'*atton NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INITIAnNG CUE START. TIME Given:

The plant is at 100% power and has just experienced a loss of SWG015

Prior to the loss of AC power, no equipment was out of service.

The crew has stabilized the plant and is in the process of determining the cause of the loss of power.

The Shift Manager has assigned you the task of determining which plant components will need to be protected based on this event. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Determine which plant components need to be protected per CNG-OP-1.01-GL012 and 5-0DP-OP5-0122.

Document your results on the provided hand out. Note: Ignore any equipment not specifically covered by 5-0DP-OP5-0122.

PERFORMANCE ACT. CODE EVALUATOR PIS INA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used JAW CNG-OP-1.01-2001, Communications and Briefings.

2. Obtain a copy of CNG-0P-1.01-GL012 and s-p SAT I UNSAT ODP-OPS-0122 and review I utilize the correct section of the procedure STD: Current version of CNG-OP-1.01-GL012 and S-ODP-OPS-0122 obtained and reviewed JAW CNG-PR-2.01-1000, Document Control. JPM SRO EC Page 6 of 15 NRC March 2014 NINE MILE POINT NUCLEAR STATION 3. PERFORMANCE Reviews any or all of the following documents to determine which plant components have been lost:

N2-SOP-03, Loss of AC Power

EE-001N, 4160V One Line Diagram, Normal Bus 2NNS-SWG015

N2-0P's, Operating Procedure Lineups

Additional EE-OOl's as applicable ACT. CODE PIS INA .Svaluators The following steps may be performed in any order. . ' EVALUATOR SAT I UNSAT STD: Obtains one or more of the listed documents and determines which components are impacted by the loss of 2NNS-SWG015.

..

'

- *.* **** ... The operator may choose to use different nomenclature to represent the affected components and equipment which will need to be protected.

This is acceptable provided it is obvious to the evaluator which components are affected and which components the operator is choosing to protect. The Evaluators Aid at the end of this JPM may be used to assist in the grading of the below steps. 4. 5. Determines the following components are affected by the loss of 2NNS-SWG015:

2RDS-P1B, CONTROL ROD DRIVE PUMP B

2CCP-P1B, REAC BLDG CLOSED LOOP COOLING WTR PUMP lB JPM SRO EC Page 7 of 15 p p *PASS/ FAIL STD: On the Handout in the cOlumn labeled "Affected Component or SyStem", documents 2RDS-P1B and/or CONTROL ROD DRIVE PUMP 8 *PAS$/ FAIL STD.: On the provided Handout in the column labeled "AffeCted Component or Systern", documents 2CCP.:.P1B and/or Reactor Bldg* dosed Loop Cooling Water Pump 18 NRC March 2014 a JO"t ventcce ot I 0 =:'lation NINE MILE POINT NUCLEAR STATION PERFORMANCE

6.

2CCP-P3B, REAC BLDG CLOSED LOOP COOLING WTR BOOSTER PUMP 3B 7.

RPM MG Set B 8.

2WCS-P1B, CLEANUP RECIRC PMP 9.

2IAS-DRY3B, IAS DRYER B 10. Reviews S-ODP-OPS-0122, Attachment 2 and determines which components need to be protected based on the following components being unavailable:

2RDS-P1B, CONTROL ROD DRIVE PUMP B JPM SRO EC Page 8 of 15 ACT. CODE PIS INA p p p p p EVALUATOR

PASS/ FAIL STD: On the pro,vid¢ in* the column labeled .. "Affected

docutnents 2CCP*P3B and/or Reactor Bldg Closed Loop Cooling Water Booster Putnp 38 *PASS/ FAIL STD: On .the provided Handout in the coltirim taiJetecl"Affected compommt or System!", documents.RPM MG Set.B . *PASS I .FAIL STD: On the provided Handout in the column labeled "Affl3c;ted Component or System*, documents 2WCS*P1B and/or CLEANUP Rt=CJRC PMP B. *PASS I FAIL. STI>: On the provided Handout in column lal:ieled "Affected CO:tnponent or System*, .documelitS 21AS-DRY3B, and/or lAS. DRYER B. *PA$5/FAIL STD: On the pro,vided Handout in the* column /abe/tid Equipment to**Protect*, document$

the. following:

CRD Putnp A Control Room Pump Control Switch

CRD.Pump A Pump .and Motbr

Breaker NRC March 2014 a pc"entuce of I NINE MILE POINT NUCLEAR STATION 11.

12.

JPM SRO EC PERFORMANCE 2CCP-P1B, REAC BLDG CLOSED LOOP COOLING WTR PUMP 1B 2CCP-P3B, REAC BLDG CLOSED LOOP COOLING WTR BOOSTER PUMP 3B Page 9 of 15 ACT. CODE P/S/NA p p EVALUATOR

PASS/ FAIL STD: On the pro.vided Handout in the column labeled "What .. Equipment.

to Protect", documents the following:

CCPcPultlp.A.

Control Room control switch

CCP PUmp A.Pump snd Motor * {keaker 2NN5-SWG012-5

.CCP Pump c Control Room Control Switch

CCP Pump C Pump and Motor *

PASS I FAIL STO: On. the provided Handout in the column labeled "What Equipment to Protect", docufTients the. following:

CCPBtxister Pump A** Control RciQm Control S.witc/1

CCP. Booster Pump A Pump .and Motor

Sneaker 2NNS-SWG013-9

CCP BoosterPump.C Control Room Control Switch

CCP Booster Pump C Pump and Mc>tor

Sneaker 2NNS-$WG014-6 NRC March 2014 CENGW a IO"t 'entuce of I Ot::*tat*on NINE MILE POINT NUCLEAR STATION 13.

14.

15.

PERFORMANCE RPM MG Set B 2WCS-P1B, CLEANUP RECIRC PMP 2IAS-DRY3B, lAS DRYER B ACT. CODE PIS INA p p p EVALUATOR

PASS I FAIL STD: On the provided Handout in the column labeled "What Equipment to Protect", documents the following:

Control Room Power Source Selector Switch

MGSetA

Breaker 2NHS-MCC008-7EL *PASS/ FAIL STD: On the provided Handout in the column labeled "What Equipment to Protect", documents the following:

WCS Pump A. Controi.Room COntrol Switch

Breaker 2NJS-US5-4D

PASS I FAIL STD: On the provided Handout in the column labeled "What Equipment to Protect", documents the following:

'A' lAS Dryer

2NJS-PNL500 CUE The Operator has completed the JPM hand out and returned it to the Evaluator.

STOP TIME JPM SRO EC Page 10 of 15 NRC March 2014 aJOI'lt venture ol-----, 0

! NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate

3. 2CCP-P3B, REAC BLDG CLOSED LOOP COOLING WTR BOOSTER PUMP 3B JPM SRO EC CRD Pump A Control Room Pump Control Switch CRD Pump A Pump and Motor Breaker 2NNS-SWG014-7 CCP Pump A Control Room Control Switch CCP Pump A Pump and Motor Breaker 2NNS-SWG012-5 CCP Pump C Control Room Control Switch CCP Pump C Pump and Motor Breaker 2NNS-SWG014-9

1. CCP Booster Pump A Control Room Control Switch 2. CCP Booster Pump A Pump and Motor 3. Breaker 2NNS-SWG013-9

4. CCP Booster Pump C Control Room Control Switch 5. CCP Booster Pump C Pump and Motor 6. Breaker 2NNS-SWG014-6

7. 8. Page 11 of 15 NRC March 2014 a JOint venture o=-..

I NINE MILE POINT NUCLEAR STATION JPM SRO EC Evaluator's Answer Key Do Not Provide to Candidate Control Room Power Source Selector Switch MG Set A Breaker 2NHS-MCC008-7EL WCS Pum A Control Room Control Switch Breaker 2NJS-US5-4D

'A' lAS Dryer 2NJS-PNLSOO Page 12 of 15 NRC March 2014 CENG .. 'JO"l "'Ieee ot I 0 =:nation NINE MILE POINT NUCLEAR STATION INITIAL CONDinONS INITXAnNG CUE JPM SRO EC JPM Handout Given:

The plant is at 100% power and has just experienced a loss of SWG015

Prior to the loss of AC power, no equipment was out of service.

The crew has stabilized the plant and is in the process of determining the cause of the loss of power.

The Shift Manager has assigned you the task of determining which plant components will need to be protected based on this event. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Determine which plant components need to be protected per CNG-OP-1.01-GL012 and 5-0DP-OP5-0122.

Document your results on the provided hand out. Note: Ignore any equipment not specifically covered by 5-0DP-OP5-0122.

Page 13 of 15 NRC March 2014 CENG .... "JO"tvectuce of I o=:w*atlon

-:,*::eoF NINE MILE POINT NUCLEAR STATION JPM SRO EC JPM Worksheet Page 14 of 15 NRC March 2014 aJOI'l!venture of __ _ O=:'a.tton

NINE MILE POINT NUCLEAR STATION JPM SRO EC Page 15 of 15 NRC March 2014 CENG_. NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC SRO Admin RC Revision:

0.0 --=-=-=----

Title: Inspection of High Radiation Areas Approvals:

Signature I Printed Name Developed

By -?----David Huff 12/18/2013 Validated By Carl Crawford 12/11/2013 Facility Reviewer Aaron Armstrong Approximate Duration : __

__ Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

Date: JPM SRO RC Page 1 of 15 NRC March 2014 8J01ntventureof--

o=*otlon -t,eDF I NINE MILE POINT NUCLEAR STATION References

1. GAP-RPP-01, Radiation Protection Program 2. GAP-RPP-02, Radiation Work Permit 3. GAP-RPP-07, Internal and External Dosimetry Program 4. GAP-RPP-08, Control of High, Locked High, and Very High Radiation Areas 5. 5-RAP-RPP-0703, Authorization to Exceed Administrative Dose Limits JPM SRO RC Page 2 of 15 NRC March 2014 a JOI'll venture of-----, o= ...

NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operators ability to evaluate radiological conditions and determine the appropriate work controls.

2. Task Information:

a. 5-RAP-RPP-08001, Control Access to Radiation Areas b. K/A .3.12 (3.7) Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc 3. Evaluation I Task Criteria Evaluation Method Perform Evaluation Location Classroom Time Critical Task No Alternate Path No LOD >1.0 Yes 4. Recommended Start Location a. Training Classroom JPM SRO RC Page 3 of 15 NRC March 2014 CENG .. " a joint ventureof--

o=llatlon -J:;eoF I NINE MILE POINT NUCLEAR STATION 5. JPM Setup (if required)

a. Make enough copies of the RWP and Survey Map for each operator to have one. b. Ensure book carts are available for the operators to use and that there is an up to date copies of the following:

1) GAP-RPP-01, Radiation Protection Program 2) GAP-RPP-02, Radiation Work Permit 3) GAP-RPP-07, Internal and External Dosimetry Program 4) GAP-RPP-08, Control of High, Locked High, and Very High Radiation Areas 5) S-RAP-RPP-0703, Authorization to Exceed Administrative Dose Limits JPM SRO RC Page 4 of 15 NRC March 2014 CENGW n )O<O"entuce of I o=:n.tlon NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM SRO RC Page 5 of 15 NRC March 2014 a JOJct 'entuce ot I -;:,eDF NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INITIATING CUE START TIME Given:

The plant is operating at 100% power.

An operator must perform a valve lineup in the RWCU Pump P1A Room.

An RWP and survey map are provided.

There are no steam leaks in the room.

The operator's current year-to-date exposure is 1800 mrem TEDE.

The operator will be performing work for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in an average radiation field of 150 mremlhr. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Address the radiological aspects of performing this lineup and record your findings on the provided worksheet PERFORMANCE ACT. CODE EVALUATOR PIS INA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary.

used lAW CNG-OP-1.01-2001, Communications and Briefings.

2. Obtain one or more of the following p SAT I UNSAT procedures and review I utilize the correct section of the procedure:

STD: Current version of listed procedures obtained and

GAP-RPP-01 reviewed lAW CNG-PR-2.01-

GAP-RPP-02 1000, Document Control .

GAP-RPP-07

GAP-RPP-08 . *,swtuatots

"*''<<;\*" ' ' The attached Evaluator Grading Sheets may be used to assist with the grading of

the below steps. Steps 3 through 8 may be performed in any order. . *' *. JPM SRO RC Page 6 of 15 NRC March 2014

0 NINE MILE POINT NUCLEAR STATION 3. 4. PERFORMANCE Addresses radiological aspects of entering RWCU Pump PlA Room for inspection as follows:

Determines the radiological classification of the area

Determines which Key is needed to access the area. ACT. CODE P/5/NA p p EVALUATOR

PASS I FAIL STD: Per (;AP-RPP-'08, and the provided su"":ey (nap[

determines the classiFic:iitiOnis

.;;; HIGH RADIATION .l4Rek *Documents the classii'Ieatii:m on the provided workSheet.

SAT I UNSAT STD: Determines per the provided survey map that KEY H-20-2 is needed to access the area. Documents the key required on the provided worksheet.

When grading Steps 5 and 6, the operator may choose to use different nomenclature to represent the locations where the highest contact dose rate and highest dose rate at 30 em is. This is acceptable, provided the location description provided by the operator is obvious to the Evaluator.

If the Evaluator EvaJuators has a question as to what location the operator is trying to describe on the 5. Note: worksheet, then the Evaluator may verbally question the operator to determine the location (i.e. the operator points to the location on the survey map). If the Evaluator verbally questions the operator as to the described locations, the answers the operator provides may be used to assist with the grading of Steps 5 and 6.

Determines the highest contact dose rate and location.

p *PASS/FAIL STD: Deteritnnes per the .. provided survey map that the highest CONTACT DOSE RATE is 230 MREM/HOUR ON THE PUMP. Documents the dose rate and location on the provided worksheet.

JPM SRO RC Page 7 of 15 NRC March 2014 CENG .. a JO"""'"'" ol I 0 =:nation NINE MILE POINT NUCLEAR STATION 6.

7. * .. PERFORMANCE Determines the highest dose rate at 30 em and location.

Determines the RWP required to be used. The Step 8 calculation is as follows: ACT. CODE P/S/NA p p

1800 mrem -Current Operator Exposure EVALUATOR

PASS/ FAIL per the provided survey map that the highest DOSE RATE AT 30 CM is 210 MREM/HOURIN THE NORTHEASTCORNER PIPING. Documents thedQ5e rate and location on .tllf!. provided worksheet.

PASS, I FAIL STD: Determin,es pet. GAP*RPP-02, a SPECIF,!C RWP SHOULD BE REQUESTED.**

Documents the specific RWP on the provided worksheet

Evaluators

The operator will work for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in a 150 mrem/hr radiation field . *:More:

Total radiation to be received is 2 x 150 = 300 mrem

Total dose the operator will have at completion of the job is 300 + 1800 = *.*\ 2100 mrem. *.-... 8.

Determines if additional approvals are p *PASS. I FAIL required for the operator.

STD: Calculates the exp¢cted exposure and determines that ADDmONAL APPROVALS WILL BE REQUI/?.ED

. Documents the need for additiOnal approvals on the.pi'o.vfded worksheet.

JPM SRO RC Page 8 of 15 NRC March 2014 8J01'1! venture of---,

...,* .... eof I Enwvv :J NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE PIS INA EVALUATOR evaluators llfote: Once the operator turns in the completed worksheet, determine if Step 8 above was completed successfully as indicated by the operator identifying that additional approvals are required for the operator to perform the work. If the operator did not correctly identify the need for approvals, then the JPM is complete and there is no need to perform the following additional steps. If the steps are not performed then they may be marked as NA. If the operator correctly identified the need for additional approvals, provide the following cue and second JPM worksheet

9. 10. ' Cue: (Operators Name), Identify the procedure and form required to be completed for the dose extension and the levels of approval needed for the dose extension.

Record your findings on the worksheet below. Provide repeat back of second initiating cue Cue: Acknowledge repeat back providing correction if necessary.

Obtains S-RAP-RPP-0703 and review I utilize the correct section of the procedure.

p p SAT I UNSAT I NA STD: Proper communications used lAW CNG-OP-1.01-2001, Communications and Briefings.

SAT I UNSAT INA STD: Current version of listed procedure obtained and reviewed lAW CNG-PR-2.01-1 000, Document Control. Evatuators Mote;*.* Steps 11 and 12 may be performed in any order. 11. Determines the additional radiological information as follows:

Determines the procedure and form required to be completed for the dose extension.

JPM SRO RC Page 9 of 15 p *PASS 1* FAIL I NA STD: Determines per RPP-0703 that ATTACHMENT 1 is required to be CQmpleted for the dose extension.

form on the worksheet provided.

NRC March 2014

'lo"t "'tuce ot I NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE EVALUATOR PIS INA 12.

Determines the approvals required for the p *PASS./.t=AIL/

NA dose extension.

TERMINATING CUE STOP TIME JPM SRO RC STD:

per S""RAP-RPP-0703, tha*t the following approvals are tecjulted:

...

Department Manger

General Sui:ltiNV.isor, of IUJdiatiOI:l PrOtection

.. Documents t{)e approvals on the workSheet provided.

The Operator has completed the JPM worksheets and returned it to the Evaluator.

The Evaluator has reviewed the worksheet to determine if any clarification is needed by the operator.

Page 10 of 15 NRC March 2014 CENG .. NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate

1. Classify the Area (check one): 0 Radiation Area ,/ High Radiation Area 0 Locked High Radiation Area 0 Very High Radiation Area 2. Designate the key to be obtained:

H-20-2 3. Designate the highest contact dose rate and the location:

230 mrem/hour, On the Pump 4. Designate the highest dose rate at 30 em and the location:

210 mrem/hour, Northeast Corner Piping 5. Designate the RWP required to be used (check one): 0 The provided RWP is acceptable

,/ A Specific RWP should be requested

6. Evaluate the exposure for the operator:

0 The expected exposure is acceptable without additional approvals

,/ Additional approval(s) (is)are required to receive the expected exposure JPM SRO RC Page 11 of 15 NRC March 2014 a JOint venture of I NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate

1. Identify the procedure and form required to be completed for the dose extension:

5-RAP-RPP-0703, Attachment 1 2. Check all appropriate boxes below for the approvals required for this dose extension: Department Manager General Supervisor of Radiation Protection D Plant General Manager D Site Vice President JPM SRO RC Page 12 of 15 NRC March 2014 CENG., a JO"""'u'e ot 1 NINE MILE POINT NUCLEAR S fATION 2"d JPM Handout and Worksheet 2nd INITIATING (Operators Name), Identify the procedure and form required to be CUE completed for the dose extension and the levels of approval needed for the dose extension.

Record your findings on the worksheet below. 1. Identify the procedure and form required to be completed for the dose extension:

2. Check all appropriate boxes below for the approvals required for this dose extension:

D Department Manager D General Supervisor of Radiation Protection D Plant General Manager D Site Vice President JPM SRO RC Page 13 of 15 NRC March 2014 CENG,. 01 JOI"t venture of o=:Hatlon I NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INITIATING CUE JPM SRO RC JPM Handout Given:

The plant is operating at 100% power.

An operator must perform a valve lineup in the RWCU Pump P1A Room.

An RWP and survey map are provided.

There are no steam leaks in the room.

The operator's current year-to-date exposure is 1800 mrem TEDE.

The operator will be performing work for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in an average radiation field of 150 mrem/hr. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Address the radiological aspects of performing this lineup and record your findings on the provided worksheet Page 14 of 15 NRC March 2014 aJOI'ltventureof--

0 =:*tatlon

-;:,eOF i ----' NINE MILE POINT NUCLEAR STATION JPM Worksheet

1. Classify the Area (check one): D Radiation Area D High Radiation Area D Locked High Radiation Area D Very High Radiation Area 2. Designate the key to be obtained:

3. Designate the highest contact dose rate and the location:

4. Designate the highest dose rate at 30 em and the location:

5. Designate the RWP required to be used (check one): D The provided RWP is acceptable D A Specific RWP should be requested

6. Evaluate the exposure for the operator:

D The expected exposure is acceptable without additional approvals D Additional approval(s) (is)are required to receive the expected exposure JPM SRO RC Page 15 of 15 NRC March 2014 NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC SRO Admin EP Revision:

0.0 ---=..:...:::...

__ _ Title: Emergency Classification (RPV Water Level, Unusual Event CU3.2) Approvals:

Developed By Validated By Facility Reviewer Signature I Printed Name 12/18/2013 Carl Crawford Aaron Armstrong Approximate Duration:

---=3:...:0:......m:...:..;..;.;in....:....:u=t=e.::....s

__ 12/11/2013 I 1.3 lc.c..l 't I Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature:

_________

_ Date: JPM SRO EP Page 1 of 13 NRC March 2014 a JOI vectuce ot I 0 =:latlon NINE MILE POINT NUCLEAR STATION References

1. EPIP-EPP-02, Classification of Emergency Conditions At Unit 2 2. Unit 2 EAL Chart JPM SRO EP Page 2 of 13 NRC March 2014 a JO""eotuce of I NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description

a. This JPM tests the operators ability to classify and declare an emergency event within 15 minutes. THE operator shall also provide verbal and written notifications within 15 minutes of declaration.

2. Task Information:

a. NS-EPL-08002, Classify an Event. b. K/A 2.4.41 (4.6) Knowledge of the emergency action level thresholds and classifications.

3. Evaluation I Task Criteria Evaluation Method Perform Evaluation Location Classroom Time Critical Task Yes Alternate Path No LOO >1.0 Yes 4. Recommended Start Location a. Training Classroom

5. JPM Setup (if required)

a. EP Packet containing the following forms in the order listed below (assembled per NAI-EPP-02):

1) EPIP-EPP-18, Attachment 1 (3 pages) JPM SRO EP Page 3 of 13 NRC March 2014 ajOI'ltventureol--

0 ='*""" -J'eoF I NINE MILE POINT NUCLEAR STATION 2) EPIP-EPP-18, Attachment 1 Figure 1 & 2 (2 pages) 3) EPIP-EPP-18, Attachment 2 (2 pages) 4) EPIP-EPP-20, Attachment 1A (2 pages) 5) EPIP-EPP-20, Attachment 4 section E (1 page) 6) EPIP-EPP-20, Attachment 6A (2 pages) 7) EPIP-EPP-20, Attachment 6B (3 pages) 8) EPIP-EPP-08, Attachment 1 ( 4 pages) 9) EPIP-EPP-18, Attachment 8 (1 page) 10) EPIP-EPP-18, Attachment 3, 4, 5, 6, 7 (1 page each) b. Copy of the current version of EPIP-EPP-02 Attachment 1, Unit 2 EAL Flowchart

c. Copy of the current version of EPIP-EPP-02-EAL, Emergency Action Level Matrix Unit 2 d. Copy of the current version of EPMP-EPP-0102, Unit 2 Emergency Classification Technical Bases e. If laminated copies used, 1) Vis-a-Vis wet erase marker(s) or equivalent

2) Wet and dry paper towel(s) or equivalent

f. Clock or timer capable of displaying minutes and seconds JPM SRO EP Page 4 of 13 NRC March 2014 a JOint venture of-------, 0 =""'lon -J,eoF I NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. C. Read Before Each Evaluated JPM 1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM SRO EP Page 5 of 13 NRC March 2014 a pot vectuce ot I 0 =:'latlon NINE MILE POINT NUCLEAR STATION INinAL CONDITIONS INinAnNG CUE I STARTnME Given:

The Plant is in mode 5.

The Reactor was shut down 5 days ago at 0100.

The Spent Fuel Pool gates are still installed

RPV water level is being raised in preparation to remove the Spent Fuel Pool gates and is currently 6 inches above the RPV flange. Then:

A recirc. loop piping leak develops on the 'A' recirc. loop that cannot be immediately isolated.

Cavity level slowly drops below the RPV flange and has been below the flange for 15 minutes.

Current level is 350 inches on shutdown range and is slowly lowering.

Radiation levels remain unchanged.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Evaluate the need to classify conditions provided per EPIP-EPP-02.

If emergency condition exists, complete the SM/ED checklist through Step 9 (Part 1 Notification Fact Sheet only) This is a Time Critical task PERFORMANCE ACT. CODE EV,ALUATOR PIS INA 1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary used per CNG-OP-1.01-2001, Communications and Briefings JPM SRO EP Page 6 of 13 NRC March 2014 a JOI!lt venture ol---, o=lation NINE MILE POINT NUCLEAR STATION PERFORMANCE

2. Obtain a copy of the SM/ED Checklist (EPIP-EPP-18 Attachment

1) and review I utilize the correct section of the procedure

3. Using the given initial conditions, the SM/ED will classify the emergency per EPIP-EPP-02 (within 15 minutes of indications available in Control Room) as a UNUSUAL EVENT per CU3.2 ACT. CODE EVALUATOR PIS INA p SAT I UNSAT STD: Preassembled SM/ED package is obtained (first five pages are EPIP-EPP-18, Att. 1) p SAT I UNSAT STD: Determines EAL CU3.2, UNUSUAL EVENT is the highest classification.

Evaluator The operator performing the JPM will take the ED responsibility.

N.ote: 4. For Site events, contact the opposite unit SM s SAT/ UNSAT and determine which SM will take the ED responsibility STD: Per EPIP-EPP-02, determines the operator will assume the role of the Cue: If Unit 1 SM contacted, report that Emergency Director.

Unit 1 is not in any EALs . . ,*artlklator.

The declaration and the time are the pass/fail criteria, NOT the reason given or the assumption of the SM/ED position.

5. Announce to Control Room staff you are now p *PA$S/ FAIL assuming SM/ED position and duties, and you are now declaring (state emergency STD: Per EPIP*EPP-18 Att. 1, ' ' j ' classification level), and provide reason for Step 4, withlr!J 15minliteSof beginplng tl1e JPM, the cifJeratdr classification/declaration/upgrade within 15 announces that an UNUSUAL minutes of the conditions being available in EVENT has *been declared per the Control Room that an EAL has been met CU3.2 or exceeded.

Time Declared JPM SRO EP Page 7 of 13 NRC March 2014 CENG .. , ato"t 'eotu*e ot I

-::,eOF NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE P /S INA EVALUATOR IF the announcement for a ground attack has been made as required by EPP-10, THEN make no further announcements until safety is assured through coordination with security.

6. 7. The SM/ED shall direct Communications Aide, Chemistry Tech and R.P. Tech to report to the Control Rooms. Cue: After approximately one minute, identify that you are reporting as the Communications Aide (Chemistry Tech and R. P. Tech if directed to report). Contact the opposite Unit control room and:

Inform SM of Drill I Actual Emergency and classification

Obtain opposite unit status

Direct SM to notify the ERO (ERONS) per EPIP-EPP-20 Attachment 4 Cue: As the Unit 1 SM, acknowledge all provided information.

Inform the operator that Unit 1 is operating at rated power. s s SAT/ UNSAT STD: Contacts the Chemistry and RP Techs and Communications Aide and directs them to report to the control room. SAT I UNSAT STD: Contacts the Unit 1 SM and informs them that this is a Drill/ Actual Emergency and provides the classification.

Additionally, directs the Unit 1 SM to notify the ERO. The operator may direct the Unit 1 SM to either ACTIVATE or NOT ACTIVATE the emergency facilities.

Either action is acceptable.

Obtains the operating status of Unit 1 EValuator I .tti: : :"

.. *. :- .. Because the classification is an Unusual Event, no evacuation is required.

However the operator has the discretion to direct an evacuation of either the protected area and/or a local area. This is an acceptable action, but not required.

8. Using EPIP-EPP-18, Attachment 1, Figure 1 flowchart determine the appropriate evacuation and accountability.

JPM SRO EP Page 8 of 13 p SAT I UNSAT STD: Determines no evacuation is required.

NRC March 2014 a JOint venture of 0

"'4*::eoF I NINE MILE POINT NUCLEAR STATION PERFORMANCE ACT. CODE P/S/NA EVALUATOR c Note= Because the classification is an Unusual Event, there are very few required blocks to be filled out by the ED on EPIP-EPP-18, Attachment 2 Emergency Announcement.

The PASS/FAIL criteria is based on providing direction to perform the announcement and not in the filling out the attachment.

9. Complete EPIP-EPP-18 Attachment 2, Emergency Announcement and direct the appropriate announcement to be made to the site. Cue: As necessary, acknowledge the direction to make the emergency announcement.

Inform the operator the emergency announcement is complete.

p *PASS/FAIL STD: Directs an operator to perform the emergency

<" " announcement.

The attached Evaluators Aid has an answer key for correctly filling out EPIP-EPP-20, Attachment 1A. Only those steps marked with a " * " and red "box" need to be filled out correctly to receive a PASS on the next step. 10. Complete EPIP-EPP-20 Attachment 1A, Part 1 Notification Fact Sheet. Include information from Unit 1 as applicable.

). p *PASS I FAIL STD: Fills out EPIP;.EPP-20 Attachment 1A per the attached answer

,'r The Comm. Aid must have time to begin roll call and check blocks for State Emergency Communications Center (SECC) and Oswego County Warning Point **

within 15 minutes of the declaration.

Handing the completed NFS Part 1 to the Comm. Aide at the 15 minute point does not meet the time requirement.

11. Provide completed Part 1A Notification Fact sheet to the Communications Aid so that off site notifications are initiated within 15 minutes of the EAL declaration Cue: As Communications Aid, accept the Part 1 Notification Fact sheet and state that you will proceed with the notifications JPM SRO EP Page 9 of 13 p *PASS/ FAIL STD: Provides.

completed Pijlrt 1 Notificatk?tj Fac.t sheet .tO the communiCations Aid within 14 minutes oi dedaraiidn NRC March 2014

a JD'""entuce ol I 0 -J,eoF NINE MILE POINT NUCLEAR STATION TERMINATI.NG CUE STOP TIME JPM SRO EP SM/ED checklist completed through Step 9 (Part 1 Notification Fact Sheet only) Page 10 of 13 NRC March 2014 a]OI'lt venture of----, 0 NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate EMERGENCY NOTIFICATIONS EPIP-EPP-20 Revision 02900 Page 15 of 38 Attachment 1A: Nine Mile Point Nuclear Station Notification Fact Sheet-Part 1 INITIAL ROLL CALL MUST BE COMPLETED BY: _____ (TIME) Sheet1of5 (Do not :MIY item:s m Pick IS! the phone. pre:ss A *. w;M about 10 then .5aY ... This i"Sio rePOrt an incident at Nine Mile Point. standby for rolll call.-r: Stale Emergency I " Oswego County I :: JA Fitzpa!rick Power Plant I " lhaff'eded NMP I Notification

Communications Center (SECCl Wiiming Pont {not req'd in 15 min) (nOC req'd in 15 min) --1. This messagtt i'S being transmitted on:(date) at (time -24 lw') viii: A. RECS B. Other 2. Tbisis: ( A.lAn iiCb.lal -UK* ( a) An Exercise 3. The Emergttney Clas"Sification i"S:

EVII!nt C. Site Area Emergency E Emergency Terminiih!d B. Alert D. General Emergency F. Other: 4. TbisE Classification was dectm!d on*.(datel Today at( time-24 hrl o! Dec. 5. of radioactift Materials due lo the classified e'ftllt: release B. Rele.ilse below federal limits {ODCM). :To atmosphere

To WatB C. Rele.ilse aboR federilllimils (ODCM), *: To atmosphere

To Wat£r D. lklrnonitored release requiring evaluation.

6. Adions n!COmmended lobe implemented as soon as jlf'.ac:tical:

need for prolective aclions outside 1he boundary B. E...acuate and ifl1llement 1he Kl Plan for the following ERPAs and all remaining ERPAs moniror the Emergency Alert System. 1 2 3 4 5 6 7 a g w 11 12 13 14 15 16 u 18 19 20 21 22 23 24 25 26 21 28 211 C. Sbefter-in-place and implement 1he Kl Plan for 1he following ERPAs AND aU remaining ERPAs monillor the Emergency AlertSvstem 1 2 3 4 56 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 2<1 25 26 27 28 29 7. U1 Brief .vent description and other significant information: (if necessary.

Do not X EAL# repeat EAL description)

U2 c::-Site 3.2 8. Re.ac:tor Statu'S:

1: {i) Shutdown {dale\ at (time

24 hr clockL__ lklit 2: A. Opet3ting Shutdown {dalel -5

-24 hr clockl. 0 1 : 0 C 9. A Elevated wind speed .L :, milesthr at 200 ft B. Ground wind speed 9 rniles.llw' at 30 ft. 10. A. Elevated wind direction (from) 11\degees at B. Ground wind direction (from) at 30ft. 200ft. 11. Stability Class: A B c D (E) F G 12. Reported by: (Ccmmunioator name\ at TeL No. (315) ASK .. Does Oswego County or New Yorfl State need further clarification on any information? (provide as appropnate)

THEN "lbis is the end of the messaal!, standby fw 1N!rification roll calC Che:k !hose invOlved State Ernetgency Communications Center I :: Os-go County I :: JA Fitzpatridl; I' , Unalfedied NMP in verification rol call {SECC) Waming Point Power Plant THEil STA 1E: "NiM Mile Point out at time:

l'time -24 hr clock) Approved by: (SMtED or ED.'RM t: Print name: Prin:: Name Si9"ii!Urec Sig:1at1.:re 0* D* D* D* D* D* JPM SRO EP Page 11 of 13 NRC March 2014 a JOI'll venture of I NINE MILE POINT NUCLEAR STATION INITIAL CONDITIONS INITIATING CUE JPM SRO EP JPM Handout Given:

The Plant is in mode 5.

The Reactor was shut down 5 days ago at 0100.

The Spent Fuel Pool gates are still installed

RPV water level is being raised in preparation to remove the Spent Fuel Pool gates and is currently 6 inches above the RPV flange. Then:

A recirc. loop piping leak develops on the 'A' recirc. loop that cannot be immediately isolated.

Cavity level slowly drops below the RPV flange and has been below the flange for 15 minutes.

Current level is 350 inches on shutdown range and is slowly lowering.

Radiation levels remain unchanged.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Evaluate the need to classify conditions provided per EPIP-EPP-02.

If emergency condition exists, complete the SM/ED checklist through Step 9 (Part 1 Notification Fact Sheet only) This is a Time Critical Task Page 12 of 13 NRC March 2014 CENG., NINE MILE POINT NUCLEAR STATION Emergency Meteorology Report Last 15 Minute Emergency Meteorology Report Data Data from Nine Mile Point Met System Date: Today Time (Local): Now Elevated Ground 200' Wind Speed (Main) 13 (mph) 30' Wind Speed (Main) 9 (mph) 200' Wind Dir From (Main) 110 (deg) 30' Wind Dir From (Main) 112 (deg) 200' Delta Temperature 0.05 (deg F) 100' Delta Temperature 0.7 (deg F) Stability Class E Stability Class c 30' Air Temperature 50 (deg F) Precipitation (15 min) 1.02 (in) JPM SRO EP Page 13 of 13 NRC March 2014 CENG M!LC P(;ii,.r:*

NUC: F:Ml 5 rJ.'0 iON Copy of __ Training Id: NRC 2013 Scenario 1 Revision:

0.0 ---'----'----

RL 2-Small break LOCA and loss of high pressure injection.

Title: Slowdown Required and recover level with low pressure ECCS Developed By Validated By Facility Reviewer NRC Scenario 1 Signature I Printed Name .4/--David Huff Michael Storms Phil MacEwen Doug Mizener (2/11/zon f2/f)/ LDIJ Aaron Armstrong

,/3/2-ol't Page 1 of 33

a pn"enturo of I 0 =:natfon ..:,eDF NINE MILE POINT NUCLEAR STATION References

1. N2-0P-101D, Power Changes 2. N2-0P-11, Service Water System 3. N2-0P-33, High Pressure Core Spray System 4. N2-SOP-30, Control Rod Drive Failures 5. N2-SOP-03, Loss of AC 6. N2-EOP-RPV, RPV Control 7. N2-EOP-PC, Primary Containment Control 8. N2-EOP-C2, RPV Slowdown 9. Unit 2 Technical Specifications Page 2 of 33 NRC Scenario 1 CENG .. a IO'""entuce of I NINE MILE POINT NUCLEAR STATION Instructor Information A. Scenario Description Sequence of Events I Expected Crew Response:

The plant is operating at 90% power with 2WCS-P1B out of service for maintenance.

The crew will take the shift and raise reactor power to 95% using recirculation flow. After the reactivity maneuver, Service Water Pump 1A will trip on motor electric fault. The crew will take action to start a standby service water pump per N2-0P-11.

When starting the standby pump, the discharge valve will fail to automatically open requiring the crew to manually open the valve. Once the standby service water pump is started, HPCS inadvertently initiates and injects into the RPV. FWLC will respond and automatically maintain RPV level below the Level 8 setpoint.

The crew will attempt to reset HPCS and place it back in standby per N2-0P-33, however the HPCS malfunction will prevent the system from being returned to standby. The crew will be required to place HPCS in pull to lock (PTL). After the HPCS pump is in PTL, suction strainer clogging will cause the running Control Rod Drive Pump to trip. The crew will take action per N2-SOP-30 and swap suction strainers.

Once the suction strainers have been swapped, the crew will restart the Rod Drive pump. Following the restoration of the Control Rod Drive Pump, a loss of both Line 5 and 6 will occur. An electrical fault will cause a complete loss of the Division 1 electrical switchgear.

A fault on the Division 2 EDG will prevent it from automatically starting.

The crew will take actions per N2-SOP-03 and manually start the Division 2 EDG and power the Division 2 electrical switchgear (CRITICAL TASK). The loss of Division 1 switchgear will require the crew to manually scram the reactor, trip the turbine, and trip Page 3 of 33 NRC Scenario 1 NOTES CENG_ a to'n"entum of I NINE MILE POINT NUCLEAR STATION both recirculation pumps. The crew will enter N2-EOP-RPV and begin actions to stabilize RPV pressure and level. After the reactor is scrammed, a small LOCA will occur. The LOCA will cause RPV level to lower. The crew will attempt to maintain level using HPCS, however once HPCS is taken out of PTL, it will trip on motor electric fault. The crew will attempt to start RCIC for level control, however it will fail to automatically start using the initiation pushbutton.

Once the crew manually starts up RCIC, it will trip on a failed pressure transmitter.

The crew will manually start the Standby Liquid Control system (SLS). When RPV level reaches the TAF, the CRS will enter N2-EOP-C2 and direct all 7 ADS valves be opened. The crew will open the ADS valves and blowdown the reactor (CRITICAL TASK). As RPV pressure lowers, the low pressure ECCS systems will begin to inject and recover RPV level. The crew will control the low pressure ECCS systems to raise RPV level back to the normal band. 1. Termination Criteria a. RPV level has been recovered above the top of active fuel. 2. Critical Tasks NOTES CT-1.0 Justification:

This task is identified as critical because without operator action to manually start the Division 2 EDG, the station would be in Station Blackout conditions.

a. CT-1.0, Given a failure of the Division 2 EDG to start, the crew will take action to manually start the Division 2 EDG IAW N2-SOP-03 CT-2.0 Justification:

This task is identified as critical because without operator action to open the 7 ADS valves, RPV water level would continue to lower until the fuel is no longer adequately cooled. Page 4 of 33 NRC Scenario 1 aJOI'lt venture of---, o=--;;,eDF I NINE MILE POINT NUCLEAR STATION b. CT-2.0, Given RPV water level at or below the TAF but above the MSCWL, the crew will open 7 ADS valves lAW N2-EOP-C2

3. Length a. rv7Q minutes 4. Mitigation Strategy Code a. RL 2-Small break LOCA or loss of high pressure injection, RPV level cannot be maintained above the top of active fuel, RPV Blowdown, recover level above TAF with low pressure systems and I or alternate coolant injection systems. 5. Technical Specifications

a. TS 3.7.1 b. TS 3.5.1 6. EAL Classification

a. Alert, FALl, ANY loss or ANY potential loss of EITHER Fuel Clad barrier OR RCS barrier. b. Table F-1, RCS Barrier A.l, B.2, C.4 c. Alert, SAl.l, AC power capability to 4.16 KV emergency buses 2ENS*SWG101 and 2ENS*SWG103 reduced to a single power source, Table S-1, 15 min. (Note 4) AND ANY additional single power source failure will result in a loss of all power to 4.16 KV emergency buses 2ENS*SWG101 and 2ENS*SWG103

7. Special Orders a. None Page 5 of 33 NRC Scenario 1 NOTES CENG'" a JO"I ventu"' of I NINE MILE POINT NOTES NUCLEAR STATION B. Initial Conditions

1. IC Number a. IC-150 2. Presets I With Triggers a. Malfunctions

1) CWlOE, 2SWP*MOV74E FAILS TO AUTO-OPEN INSERTED 2) CWlOF, 2SWP*MOV74F FAILS TO AUTO-OPEN INSERTED 3) DG04B, DIV 2 EDG FAILS TO AUTO START, INSERTED FV=TRUE 4) RCOl, RCIC AUTO START FAILURE INSERTED 5) CWOlA, SWP A TRIP, FV=TRUE TRGl 6) CSOlB, HPCS INITIATION ON LOW LEVEL, TRG2 FV=TRUE 7) RD18, CLOGGED RDS SUCTION STRAINER, TRG3 FV=TRUE 8) ED02A, LOSS OF LINE 5, FV=TRUE TRG4 9) ED02B, LOSS OF LINE 6, FV=TRUE, DT=3 TRG4 10) EDOSA, DIV 1 BUS FAULT, FV=TRUE, DT=10 TRG4 11) RR20, DBA LOCA, FV=0.5, RT=15:00 TRG15 12) RC06, RCIC TURBINE TRIP, FV=TRUE, DT=30 TRG16 13) CSOS, HPCS PUMP TRIP, FV=TRUE, DT=5 TRG17 b. Remotes 1) CWSS, 2SWP*MOV95A BKR, FV=OPEN, DT=120 TRGS 2) CW54, 2SWP*MOV95A VALVE POSITION, FV=O, TRGS DT=120 3) CWSS, 2SWP*V1230 VALVE POSITION, FV=100, TRGS DT=130 Page 6 of 33 NRC Scenario 1 CENG .. ap,tveotuceof I

NINE MILE POINT NUCLEAR STATION 4) CW59, 2SWP-V1233 VALVE POSITION, FV=OPEN, DT=130 5) DG10, HPCS LOCKOUT RESET, FV=RESET, DT=140 6) CW57, 2SWP*MOV95B BKR, FV=OPEN, DT=20 7) CW56, 2SWP*MOV95B VLV POSITION, FV=O, DT=25 8) RM02-041, SWP 23B RAD MONITOR ONLINE, FV=ON 9) RM03-041,SWP 23B RAD MONITOR SAMPLE PUMP POWER, FV=ON c. Overrides

1) None d. Annunciators

1) None e. Event Triggers *Event # Event Action 15 zdrps1d==1 (mode switch to SD) 16 hzarcr606>0.625 (RCIC flow meter >500 gpm) 17 zdrps1d==1 .and. hzacshr603>0.04 (mode switch in shutdown and HPCS flow meter >2K gpm) f. Equipment Out of Service 1) 2WCS-P1B in Pull To Lock g. Support Documentation

1) None Page 7 of 33 NRC Scenario 1 NOTES TRG5 TRG5 TRG6 TRG6 TRG7 TRG7 Command Blank Blank Blank CENG .. a Joint venture of----,

NINE MILE POINT NUCLEAR STATION SHIFT TURNOVER INFORMATION ON COMING SHIFT: J N I 0 OA TE: _,T-=o=d=-ay.___

__ PART I: To be performed by the oncoming Operator before assuming the shift.

Control Panel Walkdown (all panels) (SRO, ROs) PART II: To be reviewed by the oncoming Operator before assuming the shift.

LCO Status (SRO)

Shift Turnover Information Sheet Evolutions/General Information/Equipment Status:

Reactor Power = 90% due to Reactor Engineering request.

2WCS-P1 B is out of service for maintenance.

All LCOs are met PART Ill: Remarks/Planned Evolutions:

Raise power to 95% using Recirculation Flow per N2-0P-101 0 and provided RMI. Page 8 of 33 NRC Scenario 1 I

a joint venture of-:::=-1 NINE MILE POINT NUCLEAR STATION ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver:

Raise Power to 95%> Step: 3697 INITIAL CONDITIONS/STEP DESCRIPTION RE presence required in the Control Room?

No ../ If YES above, RE presence not required for steps Initial conditions to be verified prior to initiation of step: Parameter Expected Range Actual Parameter Expected Range Actual CTP 3600-3630 MWth Load Line <100% Time Now MFLCPR <0.90 Description of Step: 1. Raise recirculation flow to achieve 95% CTP (3783-3793 MWth) at a 25%CTP/hr rate Critical parameters to be monitored DURING Step: Critical parameters not used must be deleted OR marked N/A Critical Limit Owner Frequency Contingency Parameter MFLCPR 0.98 STA Hourly and every 5% rise Notify SM and RE Supervision; Demand in CTP and review 3D cases every 15 minutes. MFLPD or 0.97 STA Hourly and every 5% rise Notify SM and RE Supervision; Demand MAPRAT in CTP and review 3D cases every 15 minutes. Plot location on power flow map every 15 Load Line 114.5% STA hour minutes; Implement contingency RMI to lower load line. I RMI evaluated against approved power profile:

N/A D. Other Comments:

Recirculation flow adjustments may be made per Shift Manager direction at the recommendation of Reactor Engineering.

Step Prepared By: Joe Engineer Today Step Reviewed By: John Engineer Today REIST A Date RE/STA/SRO Date Approval to Perform Step: Joe Manager Shift Manager Date Step Completed By: SRO Date Page 9 of 33 NRC Scenario 1 I I CENG,. e JOi't ve,tuce of I NINE MILE POINT NUCLEAR STATION Shift Turnover Instructor Actions I Pla)lt Response Take the Simulator out of freeze before the crew enters for the pre-shift walkdown.

Verify annunciator sound turned on

If recording scenario, start the recording device during the pre-shift walkdown Allow no more than 5 minutes to walkdown the panels. NRC Scenario 1 Operator Actions Crew

Walkdown panels

Conduct shift turnover brief

Assume the shift Page 10 of 33 CENG .. a JO'n"entum ot I O=:a-1on NINE MILE POINT NUCLEAR STATION Event # 1: Raise Power to 95°/o using Recirculation Flow Event Information Event Termination Criteria NRC Scenario 1

Initial reactor power is rv9Q%

The crew will raise reactor power using Recirc to rv95% power SRO

Directs RO to raise power to 95% using Recirc flow per RMI and N2-0P-101D.

RO

Acknowledges direction to raise reactor power to 95% using Recirc flow.

Raises power to 95% by raising core flow: 0 Moves RCS*HYV17A&B individually in the open direction, maintaining loop flow differential at a minimal value by alternating between the two valves.

Monitors APRMs and rate of power change. BOP

Monitors plant parameters to verify proper operations.

Provides peer checks as needed

Reactor power has been raised sufficiently as determined by the Lead Evaluator.

Page 11 of 33 a JO"t ventuce of I NINE MILE POINT NUCLEAR STATION Event #2: Service Water Pump Trip Event Information

Service Water Pump PlA trips on motor electric fault.

Operators will respond per the ARPs and start an additional pump.

The discharge valve will not automatically open when starting the standby pump requiring operators to manually open the valve. Verify inserted the following malfunctions:

CWlOE, 2SWP*MOV74E FAILS TO AUTO-OPEN CWlOF, 2SWP*MOV74F FAILS TO AUTO-OPEN When directed by lead instructor/evaluator, insert the following malfunction:

TRGl CWOlA, SWP A TRIP, FV=TRUE Service Water Pump P1A trips The following annunciators alarm:

601113, Service Water Pump 1A/1C/1E Auto Trip Fail to Start

601114, Service Water Pump 1A/1C/1E Motor/Feeder Elec Fault NRC Scenario 1 CREW

Recognizes and reports loss of SWP PlA Page 12 of 33 CENG,. a JO'O! veotuce ot I NINE MILE POINT NUCLEAR STATION Note: The SRO may determine that a SWP must be started immediately and direct the BOP to start a pump without going through the in plant actions. This method is acceptable.

If the SRO decides on this course of action, then throttling of the MOV74's will not be required.

Role Play As PO dispatched to inspect SWP P1A, wait two minutes and inform them that the pump motor is abnormally hot to the touch and the breaker overcurrent flag is tripped. Note: The SRO may direct starting either SWP E or F Role Play As PO dispatched to perform prestart checks on SWP E or F, wait one minute and report that prestart checks have been completed satisfactorily.

Note: P&L 13. States the following:

With three operable and running SWP pumps, the plant shall restore 4 operable pumps to service in an expedited fashion. In this condition the plant is in a degraded state, see Tech Spec 3.7.1 for required actions. SRO

Directs BOP to respond to trip of SWP P1A

References TS 3.7.1 and determines

<4 operable service water pumps are in operation

Enters condition E of TS 3. 7.1 and determines he has 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore 4 service water pumps to operation.

BOP

Acknowledges direction to respond to SWP P1A trip

May contact PO and direct them to inspect SWP A pump and breaker

References ARP 60113 and determines flows on the operating SWPs are >10,000 gpm

Throttles shut on 2SWP*MOV74B, C, D to maintain flows <10,0000 gpm

Determines that time permits to start a SWP per N2-0P-11, Section E.2.0

Contacts PO and directs him to perform prestart checks of SWP E(F)

Determines conditions in P&L 13.0 are met

Verifies 2SWP*MOV74E(F)

IS SHUT Page 13 of 33 NRC Scenario 1 a JO'nt 'entuce ot I NINE MILE POINT NUCLEAR STATION Role Play As PO directed to perform steps E.2.4 through E.2.6, wait one minute and inform the control room that those steps have been complete Note: When SWP P1E(F) is started, its associated discharge valve will fail to open. Role Play As Electrical Maintenance contacted for SWP A trip, inform them you will begin working on a troubleshooting plan. NRC Scenario 1 BOP Ccont.l

Contacts PO and directs them to perform N2-0P-11, Steps E.2.4 through E.2.6 for SWP E(F)

Determines sufficient flow is available for each SWP to have at least 2500 gpm

Starts SWP E(F) by placing control switch in NORMAL AFTER START

Verifies the following parameters:

o Red running light lit. o Pump Current is ::::;76 amps. o 2SWP*MOV74E(F)opens fully. o ALL running Service Water Pump Flows are 2:::2500 gpm.

Determines that 2SWP*MOV74E(F) failed to open and manually opens MOV74E(F).

Informs SRO that SWP E(F) has been started and its associated discharge valve failed to open automatically.

May place SWP P1A control switch in PTL

Contacts Electrical Maintenance

Fully opens 2SWP*MOV74B, C, and D SRO

Acknowledges BOP report of 2SWP*MOV74E(F) failing to automatically open.

If P1E was started, declares 2SWP*P1E inoperable and determines he is still in condition E of TS 3.7.1 and also TS 3.7.1, Condition C now applies (only one operable service water pump in one division).

Determines he has 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore the Division 1 SW Subsystem to operable status. Page 14 of 33 a )O"t 'entuce of I NINE MILE POINT NUCLEAR STATION Role Play As the SM, acknowledge the report from the SRO and inform him to maintain SWP P1E(F) running until an evaluation can be made. SRO Ccont.l

If P1F was started, declares 2SWP*P1F inoperable and determines he is still in TS 3.7.1, ConditionE and has 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to start a fourth operable SWP.

Contacts SM and informs him that both SWP P1A and E(F) are inoperable.

Event Termination Criteria

2SWP*P1E(F) is running and its associated discharge valve is open. Page 15 of 33 NRC Scenario 1 CENG_ a pet 'entun> of I -;:,eoF NINE MILE POINT NUCLEAR STATION Event #3: Inadvertent Initiation of HPCS Event.

With the plant at power, an inadvertent initiation of HPCS will occur.

InfonJ1-on

FWLC will automatically respond and the plant will remain online.

The crew will take action to secure HPCS. When directed by lead instructor/evaluator, insert the following malfunction:

TRG2 CSOlB, HPCS INITIATION ON LOW LEVEL, FV=TRUE HPCS will auto start and begin injecting into the core. RPV water level will rise and FWLC will respond to lower level. MWth lowers. The following annunciators alarm:

852311 EDG 2 TROUBLE

852317 EDG2 RUNNING

603139 REACTOR WATER LEVEL HIGH/LOW NRC Scenario 1 CREW

Recognizes and reports HPCS initiation and injection into the RPV RO

Monitors RPV water level and FWLC response.

Reports to the SRO that FWLC is responding Page 16 of 33 CENG,. a JOint venture of---, o=latlon I NINE MILE POINT NUCLEAR STATION Role Play If contacted as booth to provide indication of the HPCS trip units all read normal and are not tripped. Note: The SRO may direct a normal shutdown first before directing a shutdown to inoperable status. Role Play As PO dispatched to perform running checks on HPCS diesel, acknowledge report SRO

Acknowledges report of HPCS initiation and injection into the core and FWLC responding

Directs BOP to determine if the HPCS initiation signal is valid BOP

Determines drywell pressure is < 1.68 psig

Determines RPV water level is > 108.8 inches

Goes to back panels and calls the booth for indication on the HPCS trip units

Informs the SRO that HPCS did not initiate on a valid signal SRO

Acknowledges report from BOP that HPCS did not initiate on a valid signal

Directs BOP to shutdown HPCS per N2-OP-33, Section G.3.0 or place HPCS in Pull-To-Lock BOP

Acknowledges direction to shutdown HPCS

May depresses HPCS MANUALLY OUT OF SERVICE pushbutton

Places HPCS control switch in PTL

Informs SRO that HPCS is shutdown

May contact PO and direct them to perform running checks on HPCS DG Page 17 of 33 NRC Scenario 1 CENG,. a )O>Ot 'entuffi of I 0=:-lan -t,eDF NINE MILE POINT NUCLEAR STATION Role Play As SM, acknowledge report of HPCS inadvertent initiation and inform the control room that you will contact the work week manager. SRO

Acknowledges report that HPCS is shutdown

Declares HPCS inoperable and enters TS 3.5.1 Condition B

May contact SM and inform them of HPCS initiation Event Termination Criteria

The HPCS pump is in Pull to Lock Page 18 of 33 NRC Scenario 1 CENG .. a JO"t vectuce ot I NINE MILE POINT NUCLEAR STATION Event #4: Loss of CRD due to Suction Strainer Clogging Event Information

A clogged suction strainer will cause a loss of the running CRD pump.

The crew will take action to swap suction strainers and restart the CRD pump. When directed by lead instructor/evaluator, insert the following malfunction:

TRG3 RD18, CLOGGED RDS SUCTION STRAINER, FV=TRUE The following annunciator alarms:

603318 CRD Pmp Suction Fltr Diff Press High After the CRD pump trips then:

603308 CRD Pmp 1A/1B Auto Trip

603309 CRD Pmp 1A Suet Press Low

603311 CRD Charging Wtr Press Low

603315 CRD PMP 18 Suet Press Low

603446 CRD Pmp Disch Hdr Press Low

603441 ROD DRIVE ACCUMULATOR Trouble Multiple Accumulator Trouble Alarms come in. After a period of time following the pump trip: 603316 CONTROL ROD TEMPERATURE HIGH 602324, RWCU PUMP CLG WTR TEMP HIGH NRC Scenario 1 CREW

Recognizes and reports to the SRO RDS high suction filter DP

References ARP 603318

Reports trip of RDS*P1A Page 19 of 33 a )O>Ot 'entuce of I NINE MILE POINT NUCLEAR STATION Role Play As PO directed to report accumulator pressures, wait two minutes and report that all accumulator pressures are rvlOOO psig. Role Play As PO directed to go swap RDS suction filters, wait until WCS is isolated then delete the following malfunction:

RD18, CLOGGED RDS SUCTION STRAINER Inform the RO that the RDS suction filters have been swapped. SRO

Acknowledges trip of RDS*PlA

Directs RO to enter N2-SOP-30 BOP

Recognizes and reports the accumulator trouble alarms

References AN603441:

RO o Determines which accumulators have trouble alarms by looking at the full core display o References N2-0P-30, Section F.7.0 o Contacts a PO and directs them to report accumulator pressures for the alarming accumulators o Reports to the SRO that Accumulators are all reading above 940 psig

Acknowledges direction to enter N2-SOP-30

Performs the actions of N2-SOP-30:

o Determines a RDS pump is not operating o Shifts RDS flow controller to manual and closes it o Contacts PO and directs them to swap RDS suction filters per N2-SOP-30, Section F.l.O o While waiting for the PO to swap suction filters, responds to Annunciator 602324 (when it alarms) as follows:

Throttles 2WCS*MOV200 until the service filters are on hold.

Trips WCS pump. Page 20 of 33 NRC Scenario 1 CENG,, a JO'""ecluce of I -;:,eoF NINE MILE POINT NUCLEAR STATION Role Play When contacted by the RO to verify seal flows and backfill flows, wait two minutes and say they are satisfactory.

Note: Approximately 4 minutes after trip of RDS pump, AN603316, Control Rod Temp. High will alarm. Role Play As PO dispatched to monitor CRDM temperatures, wait two minutes after start of RDS pump, (and AN603316 is clear), and report CRDM temperatures are back to normal. RO Ccont.l o Once PO reports back the suction filters have been swapped, restarts RDS*PlA o Once an RDS pump is running, adjusts the RDS flow control valve so system flow is approximately 63 gpm o Places RDS flow controller back in automatic o Contacts PO and directs them to verify WCS/RCS seal flows and backfill flows per N2-0P-30, Section F.2.5 through F.2.9 BOP

Recognizes and reports high CRDM temperature alarm

Contacts PO and dispatches them to monitor CRDM temperatures at 2RDS-TRS165 Event Criteria

CRD Suction Strainers have been swapped and a CRD pump has been restarted.

Page 21 of 33 NRC Scenario 1 CENG .. a jOint venture of---, o=:-

I NINE MILE POINT NUCLEAR STATION Event # 5: Loss of Line 5 and 6, Division 2 EDG Fails to Auto Start Information

A loss of Line 5 and 6 will occur.

Division 1 bus will not be reenergized due to a bus fault

Division 2 EDG will not auto start however it can be manually started. Verify inserted the following malfunction:

DG04B, DIV 2 EDG FAILS TO AUTO START, FV=TRUE When directed by lead instructor/evaluator, insert the following malfunction:

TRG4 ED02A, LOSS OF LINE 5, FV=TRUE ED02B, LOSS OF LINE 6, FV=TRUE, DT=3 EDOSA, DIV 1 BUS FAULT, FV=TRUE, DT=10 Power is lost to Div 1 and 2 SWG Div 1 EDG starts, but does not power its bus Div 2 EDG fails to start Division 3 EDG starts up and powers its bus CREW

Recognizes and reports loss of line 5 and 6 and failure of Div 2 EDG to automatically start SRO

Acknowledges report of loss of line 5 and 6

Directs BOP to enter N2-SOP-03 Page 22 of 33 NRC Scenario 1 a pet 'ecturn ot I o=:a.uon -!,eDF NINE MILE POINT NUCLEAR STATION Note: The crew may attempt to start the start the Division 2 EDG before dispatching an operator to align Firewater to the HPCS EDG. If this is the case, then they will be able to start the diesel and not have to supply Firewater to the HPCS EDG. Role Play As PO, if dispatched to align firewater to HPCS EDG, insert the following remote functions:

TRGS CWSS, 2SWP*MOV95A BKR, FV=OPEN, DT=120 CW54, 2SWP*MOV95A VALVE POSITION, FV=O, DT=120 CWSS, 2SWP*V1230 VALVE POSITION, FV=100, DT=130 CW59, 2SWP-V1233 VALVE POSITION, FV=OPEN, DT=130 DG10, HPCS LOCKOUT RESET, FV=RESET, DT=140 When the above remotes are in, contact the control room and confirm that flow is indicated in the control room on 2SWP*FI535.

When flow is confirmed, insert the following remote functions:

NRC Scenario 1 BOP CN2-SOP-03)

Acknowledges direction to enter N2-SOP-03

Determines HPCS EDG has started and Division I and II EDGs are not powering their bus

Using HPCS DIESEL ENGINE EMERGENCY STOP pushbutton on 2CEC*PNL852, immediately trips the HPCS Diesel.

Contacts PO and directs them to supply fire water to HPCS EDG per N2-SOP-03, Detail B

Determines both divisions lost power

Determines Division 1 EDG will not be able to power its bus due to a bus fault (Annunciators 852131 and 852148)

Determines Division 2 EDG did not start and power its bus

Attempts to manually start and load the Division II EDG as follows: o Verifies the following annunciators are not lit:

852211

852225

852227

852231

852235

852239

852247

852248 Page 23 of 33 a pc"ectuce ot I 0 =:lation .;,eoF NINE MILE POINT NUCLEAR STATION TRG6 CW57, 2SWP*MOV95B BKR, FV=OPEN, DT=20 CW56, 2SWP*MOV95B VALVE POSITION, FV=O, DT=25 Report to the control room that firewater has been aligned to the HPCS EDG CT-1.0: Given a failure of the Division 2 EDG to automatically start, the crew will take action to manually start the Division II EDG IAW N2-SOP-03 Note: Because only Division 2 has electrical power, a reactor scram will be required per N2-SOP-11.

NRC Scenario 1 BOP (N2-SOP-03} (cont.} 0 Places Division II 2EGS*EG3 control switch to START. o Verifies Emergency DSL GEN 3 frequency 60 Hz. o Verifies Emergency DSL GEN 3 voltage is 4160 V. 0 Determines that Division 2 EDG started and re-energized the Division 2 SWG

Reports to the SRO that EDG has started and is powering the Division II SWG

Informs the SRO that N2-SOP-03 requires entry into N2-SOP-11 SRO (N2-SOP-11}

Acknowledges report of Division 2 EDG running and powering its bus and the requirement to enter N2-SOP-11

Directs RO/BOP to enter N2-SOP-11.

RO/BOP (N2-SOP-11}

Acknowledges direction to enter N2-SOP-11.

Enters N2-SOP-11

Determines that SWP Non-Essential Headers are isolated and cannot be restored.

Informs the SRO that N2-SOP-11 requires the following actions: 0 Scram the reactor o Trip the Turbine o Trip both Recirculation Pumps Page 24 of 33

a ]Oint venture ol-----, o=-

I NINE MILE POINT NUCLEAR STATION E\fent Term-.tion Criteria NRC Scenario 1 SRO

Acknowledges report from BOP that a reactor scram is required.

Directs the RO to manually scram the reactor. RO CN2-SOP-11l

Acknowledges direction to manually scram the reactor.

Places the Mode Switch in SHUTDOWN .

Determines all rods inserted .

Provides Scram Report to the SRO . BOP CN2-SOP-21l

Trips the Turbine as follows per N2-SOP-21: 0 Determines power is <21% 0 Depresses both Turbine TRIP push buttons. 0 Determines the Turbine Tripped and verifies the MSVs, CVs, and CIVs closed.

Recognizes that the turbine trip caused a loss of both SWG001 and 003.

Verifies tripped both Recirculation Pumps by placing the control switches to STOP.

As timer permits, continues actions in Attachment 1 of N2-SOP-03 SRO

Acknowledges scram report .

Enters N2-EOP-RPV

Reactor is scrammed

N2-EOP-RPV is entered. Page 25 of 33 CENG .. NINE MILE POINT NUCLEAR STATION Event #6: Small LOCA and Loss of High Pressure Injection Event Information

A small LOCA and loss of high pressure injection sources will require an RPV Blowdown due to RPV Level.

RPV Level will be recovered using low pressure ECCS pumps. Note: When the crew placed the mode switch in shutdown in the previous event, the below malfunction was inserted:

RR20, DBA LOCA, FV=O.S, RT=15:00 OW pressure starts to rise slowly RPV water level starts to lower The following annunciator alarms:

851254 PROCESS AIRBORNE RADN MON ACTIVATED CREW

Recognizes and reports rising drywell pressure and lowering RPV level SRO (N2-EOP-RPVl

Acknowledges report of rising drywell pressure and lowering RPV level.

When drywell pressure reaches 1.68 psig, enters N2-EOP-PC.

Directs RO to perform actions of N2-SOP-101C

Directs RO to maintain RPV water level 160 to 200 inches using RCIC Page 26 of 33 NRC Scenario 1

a pet 'entuce ot I NINE MILE POINT NUCLEAR STATION Note: Due to the electrical failure of Division 1, the SRO may given out the order of 500 to 1000 psig using sustained opening of the SRVs instead of 800 to 1000 psig. Role Play As PO directed to energize 2WCS-MOV107, acknowledge the report. Note: Malfunctions will prevent RCIC from automatically starting with the RCIC Pushbutton.

NRC Scenario 1

Directs BOP to coordinate with the RO and maintain RPV pressure 800 to 1000 psig (500 to 1000 psig) using RCIC, supplement with SRVs RO CN2-SOP-101Cl

Acknowledges direction to take actions per N2-SOP-101C

Acknowledges direction to maintain RPV water level 160 to 200 inches using RCIC

Performs initial actions of N2-SOP-101C:

o Verifies turbine has tripped and TSV/TCVs are shut o Verifies generator has tripped and house loads have transferred o Verifies SDV vent and drain valves have closed o Verifies RCS pumps are not running o As necessary inserts SRMs and IRMs 0 May direct energizing 2WCS-MOV107 0 May shutdown HWC BOP CN2-EOP-RPVl

Acknowledges direction to coordinate with the RO and maintain RPV pressure 800-1000 (500 to 1000) psig using RCIC and supplement with SRVs

Monitors RPV pressure and cycles SRVs as necessary to maintain 800-1000 (500 to 1000) psig. RO CN2-EOP-HCl

Initiates RCIC as follows: 0 Determines RCIC is not already running, and arms AND depresses RCIC MANUAL INITIATION pushbutton 0 Determines RCIC did not start using the Page 27 of 33 CENG .. a JO"t veotuce of I NINE MILE POINT NUCLEAR STATION NRC Scenario 1 initiation pushbutton and a manual RCIC start is required.

Manually initiates RCIC as follows: o Places 2ICS*FC101 in Manual AND sets output to 20% RO (cont.) o Starts GLAND SEAL SYSTEM AIR COMPRESSOR o Opens ICS*MOV116, LUBE OIL COOLING WATER SUPPLY o Opens ICS*MOV120, TURB STM SUPPLY VLV, AND observes RCIC Turbine speed rising o Verifies open ICS*MOV143, PMP MINIMUM FLOW TO SUPPRESSION POOL o WHEN ICS*MOV120 is full open, opens ICS*MOV126, PMP 1 DISCH TO REACTOR o Slowly raises RCIC Turbine speed using RCIC FLOW CONTROLLER in Manual AND verifies the following:

RCIC Turbine speed rises on E51-C002-M1

RCIC pump discharge pressure rises on E51-R601 o WHEN RCIC pump discharge pressure exceeds reactor pressure, verifies the following:

ICS*V156, REACTOR INJECTION OUTBD CHECK VLV, opens

ICS*V157, REACTOR INJECTION INBD CHECK VLV, opens

RCIC injection flow rises on E51-R606 o WHEN system flow exceeds 220 gpm, verify ICS*MOV143, PMP MINIMUM FLOW TO SUPPRESSION POOL, closes Page 28 of 33

a pet vectuce of I 0 =:lation ..::eoF NINE MILE POINT NUCLEAR STATION After RCIC flow is above 500 gpm, verify inserted the following malfunction:

RC06, RCIC TURBINE TRIP, FV=TRUE, DT=30 RCIC trips on high turbine exhaust pressure.

rv8 seconds after HPCS starts, verify inserted the following malfunction:

CSOS, HPCS PUMP TRIP, FV=TRUE, DT=5 HPCS pump trips on motor electric fault. NRC Scenario 1 o WHEN RCIC injection flow reaches 600 gpm, place flow controller in Automatic RO (cont.)

rv30 seconds after RCIC flow reaches 500 gpm, determines that RCIC tripped and cannot be restarted.

Informs SRO that RCIC has tripped . SRO CN2-EOP-RPVl

Acknowledges report of RCIC trip .

Directs BOP to maintain RPV pressure 800-1000 psig using SRVs.

Directs RO to maintain RPV Level 160-200 inches using HPCS. RO CN2-EOP-RPV)

Acknowledges order to maintain RPV Level 160-200 inches using HPCS.

Takes HPCS control switch out of PTL

Determines that HPCS tripped on motor electric fault.

Reports to the SRO that HPCS tripped on motor electric fault. BOP CN2-EOP-RPV)

Acknowledges direction to maintain RPV pressure 800-1000 psig using SRVs only. SRO CN2-EOP-RPV)

Acknowledges report that HPCS has tripped.

Determines alternate injection systems Page 29 of 33 a pnt 'entuce of I NINE MILE POINT NUCLEAR STATION NRC Scenario 1 are needed and performs the following:

0 Directs RO to inject with SLS per N2-OP-36A, Section H.l.O SRO Ccont.l 0 Determines water level cannot be restored and maintained above -14 inches and enters center leg of N2-EOP-RPV 0 Directs BOP to inhibit ADS RO (N2-EOP-RPV)

Acknowledges direction to inject with SLS per N2-0P-36A, Section H.l.O

Injects with SLS as follows: 0 Places keylock switches for both SLS*PlB in RUN 0 Recognizes SLS PlB started as expected and all indications are normal 0 Reports to the SRO that SLS is injecting with SLS PlB BOP CN2-EOP-HCl

Acknowledges direction to inhibit ADS

Inhibits ADS by performing the following:

0 Places BOTH DIV I and Div II ADS AUTOMATIC INITIATION DISABLE keylock switches in ON

Informs the SRO that ADS is inhibited Page 30 of 33 a JOint venture of---, o=--lon I NINE MILE POINT NUCLEAR STATION Note: The SRO may also direct to lineup RHS B for injection through shutdown cooling before blowing down. This is an acceptable action but not required.

Note: At the Lead Evaluator's discretion, the following malfunction may be adjusted to raise or lower the rate at which RPV level is lowering:

RR20, DBA LOCA CT -2.0 Given RPV level at or below the TAF but above the MSCWL, the crew will open 7 ADS valves lAW N2-EOP-C2 CT-2.0 Given RPV level at or below the TAF but above the MSCWL, the crew will open 7 ADS valves lAW N2-EOP-C2 Note: As RPV pressure lowers, LPCI B and C will inject and RPV level will begin to rapidly rise. NRC Scenario 1 SRO (N2-EOP-RPV and N2-EOP-C2}

Determines at least two injection systems are lined up

Waits until RPV water level is at TAF

Determines LPCI Band C ECCS systems are lined up with a pump running

Waits until RPV water level is at TAF

Determines LPCI Band C ECCS systems are lined up with a pump running

Enters N2-EOP-C2, RPV Slowdown:

0 Determines Reactor will stay shutdown without boron 0 Determines drywell pressure is above 1.68 psig 0 Determines there is no need to prevent LPCI or LPCS injection 0 Determines suppression pool level is >192 feet 0 Directs BOP to open 7 ADS valves. BOP (N2-EOP-HC}

Acknowledges direction to open 7 ADS valves and performs the following:

0 Determines no SRVs are stuck open and an ECCS pump is running o Arms and depresses both ADS pushbuttons for each division o Informs the SRO that 7 ADS valves are open

Verifies LPCI B and C ECCS systems inject when pressure is lowered sufficiently SRO (N2-EOP-RPV}

Acknowledges report from BOP that 7 ADS valves are open Page 31 of 33 a jo"t ventu"' of I NINE MILE POINT NUCLEAR STATION Note Actions in EOP-RPV regarding establishing adequate core cooling will be prioritized, however as systems become available, the SRO may choose to use systems as necessary to mitigate primary containment parameters NRC Scenario 1 SRO {cont.)

Directs BOP to inject with all available injection system to restore RPV level >MSCWL

As water level rises above MSCWL and TAF, directs RO to secure injection sources as necessary to establish and maintain an RPV water level of 160 to 200 inches

May direct BOP to remove RHS B and place it into suppression chamber sprays per N2-EOP-6, Attachment 22 SRO, {N2-EOP-PCl

Determines DW pressure cannot be maintained

<1.68 psig

Directs BOP to place suppression chamber sprays in service on RHS B per N2-EOP-6.22 BOP {N2-EOP-6.22l

Acknowledges direction from SRO to spray the suppression chamber using RHS B: o Verifies open MOV90B o Verifies shut and overridden MOV24B o Verifies RHS B is running o Verifies open 2RHS*MOV33B o Throttles open 2SWP*MOV33B as necessary to establish service water flow to RHS heat exchanger Page 32 of 33

a)Oirtt venture of---, 0=--'"'" -J,eDF I NINE MILE POINT NUCLEAR STATION Role Play As RP contacted to place RE-23B in service, wait two minutes and insert the following remote function : TRG7 RM02-041, SWP 23B RAD MONITOR ONLINE, FV=ON RM03-041,SWP 23B RAD MONITOR SAMPLE PUMP POWER, FV=ON Report back to control room that RE-23B is in service

7 SRVs are open o Contacts RP to place RE-23A(B) in service

Informs the SRO that RHS B is in suppression chamber sprays Event Criteria

RPV Water Level is above the TAF and being recovered "+,_,"' '>', Page 33 of 33 NRC Scenario 1 CENG_

MILE POINT i\:UCLEAR STAT!ON Copy of __ Training Id: NRC 2013 Scenario 2 Revision:

0.0 ___:::...:....::....

__ _ PC 4, High containment pressure approaching PCPL, exceeds PSP, Title: RPV Slowdown required Developed By Validated By Facility Reviewer NRC Scenario 2 Signature I Printed Name David Huff Michael Storms Phil MacEwen Doug Mizener Aaron Armstrong Page 1 of 42 )2/17/?flJ) 12/n}zo *,3 a JOint venture of----, 0 =""""" -;:,eoF I NINE MILE POINT NUCLEAR STATION References

1. N2-0P-101D, Power Changes 2. N2-0P-92, Neutron Monitoring System 3. N2-0P-25, Auxiliary Steam, Auxiliary Condensate, and Gland Seal 4. N2-SOP-97, RPS Failures 5. N2-SOP-11, Loss or Degraded Service Water 6. N2-EOP-RPV, RPV Control 7. N2-EOP-PC, Primary Containment Control 8. N2-EOP-C2, RPV Slowdown 9. Unit 2 Technical Specifications Page 2 of 42 NRC Scenario 2

a jOint venture of---, O=:o-I NINE MILE POINT NUCLEAR STATION Instructor Information A. Scenario Description The crew will take the shift at IV65% power. The shutdown is on hold pending surveillance results. Instrument Air Compressor C is out of service due to maintenance.

After the crew takes the shift, a malfunction in the normal station service transformer cooling system causes transformer temperatures to rise. The crew will dispatch a PO to investigate.

The PO will report that several of the transformer cooling fans are not running and cannot be started. The crew will coordinate with the PO and lower power per N2-SOP-101D to stabilize transformer temperatures.

Once temperatures are under control, APRM 2 will fail upscale. The crew will take action per the ARP's and N2-0P-92 to bypass APRM 2. The CRS will evaluate TS 3.3.1.1 for the inoperable APRM. Once APRM 2 is bypassed, the running Gland Seal Exhaust Fan will trip on motor electric fault. The crew will take action per the ARP's and N2-0P-25 to isolate the tripped Gland Seal Exhaust Fan and start a standby fan. After the Gland Seal Exhaust Fan is started, the RPS B Motor Generator will trip causing a half scram on RPS B side. The crew will enter N2-SOP-97 and align the RPS B solenoids to their alternate power supply. While resetting the EPA's per N2-SOP-97, the Plant Operator will report that the undervoltage trip relay had to be bypassed in order to reset one of the EPA's. The CRS will declare the associated EPA inoperable and evaluate TS 3.3.8.3. After the RPS B solenoids are powered from their alternate power supply, Service Water intake clogging will occur causing Service Water intake bay level to lower. The crew will take action per N2-SOP-11 and attempt to clean the traveling screens. Intake bay will continue to lower to 234 feet. The intake bay bypass valves 2SWP*MOV77A/B will fail to automatically open requiring the crew Page 3 of 42 NRC Scenario 2 NOTES CENG .. a JOint venture of I NINE MILE POINT NUCLEAR STATION to take manual action to open the valves (CRITICAL TASK). Once MOV77A and Bare open, intake bay level will recover. Once Service Water intake bay level is restored, a loss of all feed pumps will occur. The loss will require the crew to place the Mode Switch in shutdown.

Once RPV level has been stabilized using alternate level control systems, a LOCA will occur. The LOCA will cause Primary Containment (PC) parameters to degrade and the crew will enter N2-EOP-PC to stabilize PC parameters.

Malfunctions in the Division 1 RHS systems will prevent RHS A from being used for primary containment control and the crew will be required to use RHS B to spray the suppression chamber. As PC conditions continue to degrade, the crew will attempt to spray the drywell using RHS B. While the crew is attempting to align drywell sprays, 2RHS*MOV25B (Drywell Spray Valve) will stick shut. Plant Operators will be dispatched in an attempt to manually open MOV25B. While the POs are attempting to manually open MOV25B, primary containment parameters will continue to degrade. The CRS will determine that Suppression Chamber Pressure cannot be restored and maintained within the Pressure Suppression Limit and will enter N2-EOP-C2 and direct 7 ADS valve be opened. The crew will open 7 SRV's and blowdown the reactor (CRITICAL TASK). The scenario may be terminated once 7 SRV's are opened. 1. Termination Criteria a. 7 SRV's are open. Page 4 of 42 NRC Scenario 2 NOTES BJO'" 'ectuce ot I NINE MILE POINT NUCLEAR STATION 2. Critical Tasks NOTES CT-1.0 Justification:

This task is identified as critical because without operator action, the plant will lose its ultimate heat sink. a. CT-1.0, Given service water intake bay level less than 234ft and a failure of 2SWP*MOV77A

& 77B to automatically open, the crew will take action to manually open 2SWP*MOV77A

& 77B per N2-SOP-11.

CT-2.0 Justification:

This task is identified as critical because without operator action the primary containment pressure suppression function would continue to degrade and would not be able to accept a full blowdown of the reactor. b. CT-2.0, Given Suppression Chamber Pressure unable to be restored and maintained within the Pressure Suppression Limit, the crew will open 7 SRV's lAW N2-EOP-C2. 3. Length a. "'80 minutes 4. Mitigation Strategy Code a. PC 4, High containment pressure approaching PCPL, exceeds PSP, RPV Slowdown required 5. Technical Specifications

a. TS 3.3.1.1 b. TS 3.3.8.3 6. EAL Classification

a. Alert, FA1.1, ANY loss or ANY potential loss of EITHER Fuel Clad barrier OR RCS barrier. b. Table F-1, RCS Barrier B.2, C.4 7. Special Orders a. None Page 5 of 42 NRC Scenario 2 CENG .. a JO"t ventuce of I 0=--ton NINE MILE POINT NOTES NUCLEAR STATION B. Initial Conditions

1. IC Number a. IC-151 2. Presets I With Triggers a. Malfunctions

1) ED16, Main Transformer Loss of Cooling, FV = 89 INSERTED 2) RH14A, ECCS FAILS TO INITIATE (DIV 1), INSERTED FV=TRUE 3) RHlOB, RHS*MOV25BJAMMED,FV=TRUE INSERTED 4) NM11B, APRM 2 FAIL UPSCALE, FV=TRUE TRGl 5) MS20A, GLAND SEAL EXHAUST FAN TRIP, TRG2 FV=TRUE 6) RP06B, LOSS OF MOTOR GENERATOR MG01B, TRG3 FV=TRUE 7) CW09, SW INTAKE CLOGGING, FV=50, RT=4:00 TRGS 8) RR20, DBA LOCA, FV=1.5, RT=15:00 TRG6 9) FW03A, FEED PUMP TRIP (P1A) FV=TRUE TRG6 10) FW03B, FEED PUMP TRIP (P1B) FV=TRUE, DT=3 TRG6 11) FW03C, FEED PUMP TRIP (P1C) FV=TRUE, DT=15 TRG7 12) RD12A, CRD FEED PUMP TRIP (P1A) FV=TRUE TRGS 13) RD12B, CRD FEED PUMP TRIP (P1B) FV=TRUE, TRGS DT=3 b. Remotes 1) CW26, 2SWP*MOV77A/B FAIL TO AUTO OPEN, INSERTED FV=TRUE 2) RP02, RPS MG2 EPA, FV=RESET TRG4 Page 6 of 42 NRC Scenario 2 CENG,. a JO"t veoMe ol I NINE MILE POINT NUCLEAR STATION 3) RM02-041, SWP 23B RAD MONITOR ONLINE, FV=ON 4) RM03-041, SWP 23B RAD MONITOR SAMPLE PUMP POWER, FV=ON c. Overrides

1) DI03513, RHS A SWITCH IN PTL, FV=OFF 2) DI03514, RHS A SWITCH IN STOP, FV=OFF 3) DI03515, RHS A SWITCH IN NORMAL AFTER STOP, FV=ON 4) DI0360, RHS A SWITCH IN NORMAL AFTER START, FV=OFF 5) DI0361, RHS A SWITCH IN START, FV=OFF d. Annunciators

1) None e. Event Triggers NOTES TRG9 TRG9 INSERTED INSERTED INSERTED INSERTED INSERTED Event #. EVent ACtion command 6 zdrps1d==1 (mode switch to shutdown)

Blank 7 zdrps1d==1 .and. zdfwsc11(2)==1 Blank (mode switch to shutdown and Feed Pump C control switch to start) 8 zdrps1d==1 .and. zdrd001b(2)==1 Blank (mode switch to shutdown and RDS Pump B control switch to start) f. Equipment Out of Service 1) Instrument Air Compressor C is out of service for maintenance.

Red Tag compressor switch in PTL and protect lAS A and B g. Support Documentation

1) None Page 7 of 42 NRC Scenario 2 CENG_ a JOint venture of-:-=--1 o=:llation NINE MILE POINT NUCLEAR STATION SHIFT TURNOVER INFORMATION ON COMING SHIFT: J N I D DATE: --=T-=o=d=a..._y

__ _ PART I: To be performed by the oncoming Operator before assuming the shift.

Control Panel Walkdown (all panels) (SRO, ROs) PART II: To be reviewed by the oncoming Operator before assuming the shift.

LCO Status (SRO)

Shift Turnover Information Sheet Evolutions/General Information/Equipment Status:

Reactor Power -65% and in the process of shutting down

Shutdown is on hold awaiting surveillance testing results. Results are expected in -3 hrs.

lAS Compressor C is red tagged for maintenance.

All LCOs are met PART Ill: Remarks/Planned Evolutions:

There are no evolutions planned for the next 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months of shift. Page 8 of 42 NRC Scenario 2 CENG .. a JO"I ventu"' of I NINE MILE POINT NUCLEAR STATION Shift Turnover "' . InStructor:A4:tto;ns 1

Take the Simulator out of freeze before the crew enters for the pre-shift walkdown.

Verify annunciator sound turned on

If recording scenario, start the recording device during the pre-shift walkdown Allow no more than 5 minutes to walkdown the panels. NRC Scenario 2 Actions Crew

Walkdown panels

Conduct shift turnover brief

Assume the shift Page 9 of 42 a pnt 'entuce of I t.J,eoF NINE MILE POINT NUCLEAR STATION Event # 1: Main Transformer Overheat **Event Information

Initial reactor power is tv65%

The crew will respond to an overheating main transformer by reducing MVARs and reactor power. Verify inserted the following malfunction and ensure transformer temperatures have stabilized:

ED16, Main Transformer Loss of Cooling, FV = 89 When directed by the lead evaluator, modify the following malfunction:

ED16, Main Transformer Loss of Cooling, FV = 100 The following computer point alarms after tv1,5 minutes:

SPMTC01, MN XFMR XM1A OIL TEMP The following annunciator alarms:

852618, Main XFMR 1A/18/1C/1D Oil System Trouble Crew

Recognizes 1 reports annunciator 852618 SRO

Acknowledges report annunciator 852618

Directs BOP to respond per the ARP BOP

Determines computer point SPMTC01 in alarm and references ARP 852618 Page 10 of 42 NRC Scenario 2 ajOI'll venture of---, o=--;;,eDF I NINE MILE POINT NUCLEAR STATION Role Play: When directed as field operator to investigate local main transformer oil temperatures and indications, wait 3 minutes and report that local gauge temperature indicates 100°C and rising slowly and it appears one bank of the cooling fans are not running. Attempts to start the additional cooling fans have not been successful.

Also, if asked, both oil pumps are running. Role Play: If asked, report that the red alarm light on the gas analyzer is not lit. Role Play: If asked to verify breaker status for transformer cooling, report the following status for only those breakers requested:

Circuit Breaker 8-3 Group No. 1 on

Circuit Breaker 8-4 Group No. 2 Cooler -on

Circuit Breaker 8P-1 Pump No. 1 -on

Circuit Breaker 8P-1 Pump No. 2 -on

2NJS-US4-4D normal supply breaker to 2MTX-XM1A-on

2NJS-US4-11C alternate supply breaker to 2MTX-XM1A-on Role Play: When requested by the control room for a temperature update, report local gauge main transformer temperatures indicate 103°C and rising slowly. As necessary, continue to provide indication of up to 105°C NRC Scenario 2

Dispatches Field Operator to investigate local temperature indications

May ask field operator if red Alarm light on gas analyzer is lit

May contact a PO and ask them to check the breaker status for the transformer cooling fans.

Determines that local gauge temperature will exceed 105°C.

Informs the SRO that: o A MVAR reduction is required o A rapid power reduction is required per N2-SOP-101D.

Page 11 of 42 a JO'C"enlute of I -;:,eoF NINE MILE POINT NUCLEAR STATION Note: The SRO may direct MVAR reduction without contacting power control. Role Play: If contacted as power control, report that a reduction in MVAR to 0 MVAR's (unity) is permissible NRC Scenario 2 SRO

Acknowledges report from BOP of the need to reduce MVAR loading and reduce reactor power per N2-SOP-101D

Directs RO to enter N2-SOP-101D and lower reactor power using Rods and/or Recirc.

May direct BOP to contact power control for guidance to reduce MVAR loading BOP

May contact power control to determine what value of MVAR loading is acceptable

Informs SRO that power control can support an MVAR reduction to 0 MVAR CRS

Directs BOP to reduce generator MVAR's to 0 MVAR BOP

Acknowledges direction to reduce generator MVAR loading

Using the guidance of N2-0P-68, reduces MVAR loading by lowering the Main Generator AC Voltage Regulator control switch position until 0 MVAR is indicated on the Main Generator MEGVARS meter

Reports to CRS that main generator VARS have been adjusted to 0 MVAR's Page 12 of 42 CENG .. a ]Oint venture ol---, o=-

I NINE MILE POINT NUCLEAR STATION Role Play: When contacted as field operator to provide local main transformer temperatures report that local gauge temperature indicates 105°C and rising slowly, but the rate of temperature rise has slowed. Once power has been lowered at least 5%, give a report that temperatures are beginning to lower and delete the following malfunction:

ED16, Main Transformer Loss of Cooling RO

Acknowledges direction to enter N2-SOP-101D to reduce power

Determines that Core flow is > 60 Mlbm/hr

Determines that core power/flow is not above the MELLLA boundary

Determines that Reactor Manual Control is available

Lowers reactor power to pre-established power level using recirculation flow control and or rods. BOP

Contacts field operator to request to update local temperature indication

Informs the SRO and RO that transformer temperatures have begun to lower. CRS

Acknowledges report that main transformer temperature is lowering.

Event Termination .

.. ********

Reactor power has been lowered sufficiently as determined by the Lead Evaluator . *.* Page 13 of 42 NRC Scenario 2 a JO'Ot ventuce of I NINE MILE POINT NUCLEAR STATION Event #2: APRM 2 Fails Upscale

APRM 2 fails upscale Event InfC)nn.ation*

The crew will respond per the ARP's and bypass APRM 2 When directed by lead evaluator, insert the following malfunction:

TRGl NM11B, APRM 2 FAIL UPSCALE, FV=TRUE APRM 2 indication will fail upscale The following annunciators alarms:

603202, APRM Trip System Upscale/Inoperable

603208, APRM Trip System Upscale

603442, Control Rod Out Block CREW

Recognizes and reports APRM 2 failure SRO

Acknowledges report of the APRM 2 failure

Directs RO to respond per the ARP's RO

Acknowledges direction to respond per the ARPs.

Refers to ARP 603202 and/or 603208

Informs the SRO that APRM 2 may be bypassed per N2-0P-92 SRO

Acknowledges report that APRM 2 may be bypassed.

Directs RO to bypass APRM 2 . Page 14 of 42 NRC Scenario 2 a)otntventureof-----, 0=""""'"

I NINE MILE POINT NUCLEAR STATION The following annunciators clear:

603202, APRM Trip System Upscale/Inoperable

603208, APRM Trip System Upscale

603442, Control Rod Out Block Role Play As the booth operator, inform the BOP that APRM 2 indicates bypassed on all 2/4 MDL modules. NRC Scenario 2 RO

Acknowledges report to bypass APRM 2

References N2-0P-92 and bypasses APRM 2 as follows: 0 Determines no other APRM is bypassed.

o Performs a channel check by verifying APRM 1, 3, and 4 are all reading within 2% of each other. o Places the APRM BYPASS joystick to the "2" position o Verifies APRM 2 BYPASS light on 2CEC*PNL603 is lit. o Asks the BOP to go to the back panel and verify APRM 2 bypass indications BOP

Verifies APRM 2 is bypassed in the back panels as follows: o Determines that "BYP" is displayed in inverse video in the header for APRM 2 o Determines the blue BYPASSED LED is lit for APRM 2 on the 2/4 MDL o Contacts the booth and asks for the BYPASSED LED 2/4 MDL indications on APRMs 1, 3, and 4.

Informs the RO that APRM 2 indicates bypassed on the back panels. RO

Acknowledges report from BOP that APRM 2 indicates bypassed on the back panels.

Informs the SRO that APRM 2 has been bypassed per N2-0P-92.

May continue on with ARP 603200 actions and ask the BOP to reset the memories on the 2/4 MDL Modules per N2-0P-92, Section F.4.0. Page 15 of 42 CENG .. a JOint venture of o=--::,eDF I NINE MILE POINT NUCLEAR STATION Role Play As the booth operator, inform the BOP that all memories have been cleared on the 2/4 MDL Modules for APRMs 1, 3, and 4. Role Play As the SM, acknowledge the failed APRM 2 and inform the SRO that you will contact I&C and inform them of the failure. BOP

May reset the 2/4 MDL Modules per N2-0P-92, Section F.4.0 as follows: o Depresses the TRIP MEMORY RESET pushbutton for APRM 2 on the 2/4 MDL Module. o Observes that all Red and Yellow LEOs are extinguished on the 2/4 Module. o Contacts the booth and directs them to Depresses the TRIP MEMORY RESET pushbutton for APRM 1, 3, and 4.

Informs the RO that the 2/4 MDL Module memories have been cleared. SRO

Acknowledges report from RO that APRM 2 is bypassed.

References TS 3.3.1.1, Table 3.3.1.1-1 and no additional actions are required due to APRMs 1, 3, and 4 being still operable.

May contact the SM and inform him of the APRM 2 Failure. Event l-.IUltion Crit:eria

APRM 2 bypassed and the SRO has referenced TS 3.3.1.1. Page 16 of 42 NRC Scenario 2 CENG .. a pet vectuce ot I 0 NINE MILE POINT NUCLEAR STATION Event #3: Gland Seal Exhaust Fan Trip . Information

.*

A trip of the running gland seal exhaust fan will occur.

The crew will take action to start a standby exhaust fan. When directed by lead evaluator, insert the following malfunction:

TRG2 MS20A, GLAND SEAL EXHAUST FAN TRIP, FV=TRUE Steam Packing Exhaust Blower Fan 1A trips on motor electrical fault Steam seal exhaust vacuum begins to degrade as read on 2TME-PI108 The following annunciators alarm:

851211, Gland Seal Exhaust Fan 1A/1B/2A/2B Mot Temp High

851201, Gland Seal Exhaust Fan 1A/1B/2A/2B Mot Overload

851231, Gland Seal Exhaust Fan 1A/1B/2A/2B Auto TRIP/FTS The following annunciator alarms approximately 2 minutes after event initiation:

851203, Gland Seal Exhaust Fan 1A/1B/2A/2B Vacuum Low NRC Scenario 2 CREW

Recognizes and reports TRIP OF Gland Seal Exhaust Fan lA. Page 17 of 42 a jo"t veotuce of I -;:,eOF NINE MILE POINT NUCLEAR STATION Note: The BOP may choose to start FN1B, 2A, or 2B. Role Play If dispatched as PO to investigate the trip of TME-FN1A, wait 2 minutes and then report that the power supply breaker is tripped with no visible indications why and that TME-FN1A looks O.K. no visible signs of damage NRC Scenario 2 SRO

Acknowledges report of the trip of Gland Seal Exhaust Fan 1A.

Directs BOP to respond per the ARPs BOP

Acknowledges direction to respond per the ARPs.

References ARP 851201 and 861203 and performs the following:

0 Determines that no steam packing exhausters are running 0 Closes TME-MOV22A, steam packing exhaust fan 1A inlet valve 0 Determines that ARP 851201 requires the standby TME fan be started using N2-0P-25.

References N2-0P-25 and performs the following:

o Throttles open 2TME-MOV22B(23A, 23B), steam packing exhaust fan 1B(2A, 2B) inlet valve 0 Starts TME-FN1B(2A, 2B)

Throttles 2TME-MOV22B(23A, 23B) to achieve 10-14 inches vacuum on the TME System

Dispatches a PO to investigate the trip of TME-FN1A RO

Monitors RPV parameters and Main Condenser Vacuum Page 18 of 42 CENG,. a pet vectuce of I NINE MILE POINT NUCLEAR STATION Note: The SRO may choose to enter N2-SOP-09 to establish extra monitoring of condenser vacuum. This is not necessary but it is an acceptable action, however no actions should be taken in SOP-09, only monitoring.

Role Play As SM, acknowledge the report for trip of the exhaust fan and inform the SRO that you will take action to inform the WWM and maintenance groups. * .. SRO

May enter N2-SOP-09, Loss of Condenser Vacuum.

Contacts SM and reports that Gland Seal Exhaust Fan 1A tripped on motor electric fault. Event Termination c*.

Gland Seal Exhaust Fan 1B(2A, 2B) is running and Gland Seal Exhaust Pressure is being controlled between 10 to 14 inches of vacuum Criteria Page 19 of 42 NRC Scenario 2 a JO"t ventu"' ol I 0=:-.tton NINE MILE POINT NUCLEAR STATION Event #4: Trip of RPS B MG Set Event. , Information

A trip will occur of RPS B MG Set.

The crew will respond per N2-SOP-97 to transfer power to the alternate power supply and reset the EPA's. Note: At the lead evaluator's discretion, this event may be initiated prior to the end of the previous event. When directed by lead instructor/evaluator, insert the following malfunction:

TRG3 RP06B, LOSS OF MOTOR GENERATOR MGOlB, FV=TRUE The four white RPS power lights for RPS B go out. Note: The SRO may assign N2-SOP-97 to either the BOP or RO, however some actions of N2-SOP-97 are in the back panels so if the RO is taking actions per N2-SOP-97, he must either turn over the OATC position to the BOP, or transfer action of N2-SOP-97 to the BOP. NRC Scenario 2 CREW

Recognizes and reports the loss of RPS MG Set B. SRO

Acknowledges report for trip of MG Set B

Directs RO to enter N2-SOP-97 Page 20 of 42 CENG,. a JO>Ot ventuce of I NINE MILE POINT NUCLEAR STATION Role Play As PO directed to check the EPAs and MG set, wait one minute and inform the control room that the RPS B RPM-EPAs are tripped, the B RPM-MG set is not running and the B RPS MG set supply breaker is closed Role Play As PO directed to adjust the MG set, wait one minute and inform the control room that the B MG set output switch is OFF and the MOTOR OFF pushbutton was depressed until the green light was lit. NRC Scenario 2 RO

Acknowledges direction to enter N2-SOP-97

Performs the following actions per N2-SOP-97: o Makes an announcement to stop any half scram or isolation testing o Determines cause of entry into N2-SOP-97 is due to loss of scram solenoid power o Determines all lights are out on the B trip system o Determines the power source selector switch is in NORM o Contacts PO and directs him to check:

RPM-EPAs

RPM-MG set

MG set supply breakers o Determines the MG set is not running o Directs PO to place output switch for B MG set to OFF and hold MOTOR OFF pushbutton until green light is lit o Determines the ALT B FEED AVAILABLE light is illuminated at PNL610 o Places the power source selector switch for MG set B in ALT B Page 21 of 42 CENG .. a IO<'I 'entuce of I NINE MILE POINT NUCLEAR STATION Role Plax As PO directed to reset the A RPM-EPAs, wait one minute and insert the following remote function:

TRG4 RP02, RPS MG2 EPA, FV=RESET Inform the control room that the B RPM-EPAs have been reset, however the UNDERVOLTAGE RELAY on ACBlB could not initially be reset and you had to bypass the relay using the red knife switch before it would reset. Role Plax As SM, acknowledge the report for trip of the MG Set and inform the SRO that you will take action to inform the WWM and maintenance groups. RO Ccont.l o Contacts PO and directs them to attempt to reset the RPS B EPAs per N2-SOP-97, Detail B o Acknowledges report from PO that the UNDERVOLTAGE RELAY on ACBlA had to be bypassed prior to resetting the EPA. o Determines the 4 white RPS solenoid lights are on at P603. o Informs SRO that the RPS A solenoids have been reenergized and the UNDERVOLTAGE RELAY on ACBlA had to be bypassed.

SRO

Acknowledges report that the UNDERVOLTAGE RELAY on ACBlB had to be bypassed.

Declares ACBlB inoperable

References TS 3.3.8.3 and enters Condition A, based on one EPA breaker being inoperable.

Contacts the SM and informs him of the loss of MG set and inoperable EPA

..

RPS B Scram Solenoids energized from their alternate power supply

TS 3.3.8.3 referenced.

Page 22 of 42 NRC Scenario 2

a JO'ot ventuce of I NINE MILE POINT NUCLEAR STATION Event # 5: Clogging of Service Water Traveling Screens Event.

A clogging of service water traveling screens will cause Service Water Intake Bay level to lower.

Operators will take action to monitor and ultimately open the traveling screen bypass valves to restore intake bay level. Note: This event takes several minutes before an annunciator alerts the crew to a problem with the service water system. At the discretion of the lead evaluator, this malfunction may be inserted prior to completing the previous event. Verify inserted the following remote function:

CW26, 2SWP*MOV77A/B FAIL TO AUTO OPEN, FV=TRUE When directed by lead evaluator, insert the following malfunction:

TRGS CW09, SW INTAKE CLOGGING, FV=SO, RT=4:00 Expected Annunciators:

601124 TRAVELING SCREEN WASH SYSTEM TROUBLE (first alarm) After a period of time: 601115 SWP PUMP 1A/C/E SUCTION PRESSURE LOW 601127 SWP INTAKE BAY WATER LEVEL LOW 601218 SWP PUMP 1B/D/F SUCTION PRESSURE LOW NRC Scenario 2 Page 23 of 42 a JO'C"ectuce ot I NINE MILE POINT NUCLEAR STATION Note: When Service Water Intake Bay Level reaches 238 feet ( "'6 min.), modify the following malfunction:

Role Play CW09, SW INTAKE CLOGGING, FV=30 As PO dispatched to investigate the trash rakes and travelling screens, wait two minutes and report that the travelling screens are clogged with debris but no additional debris is coming in. As necessary, respond to the control room that you are attempting to clean the travelling screens Role Play As PO dispatched to verify proper operation of the traveling screens and trash rakes per N2-0P-12, acknowledge report. NRC Scenario 2 CREW

May identify that SW intake bay level is lowering prior to any annunciator

Recognizes and reports Annunciator 601124 SRO

Acknowledges report

Directs actions per appropriate ARPs BOP

Contacts PO and dispatches them to inspect and report the status of the trash rakes and traveling screens

Recognizes and reports SW intake bay level lowering SRO

Acknowledges report of lowering intake bay level

Directs BOP to enter N2-SOP-11 BOP

Acknowledges direction to enter N2-SOP-11

Contacts PO and dispatches them to verify proper operation of traveling screens and trash racks per N2-0P-12

Trips the Jet Motive Pump (SWP-P3)

When intake bay level lowers to 238 feet, verifies 2SWP*MOV30A/B are open Page 24 of 42 CENG .. a JOint venture of---,

I NINE MILE POINT NUCLEAR STATION CT-1.0 Given service water intake bay level less than 234 ft and a failure of 2SWP*MOV77A

& 77B to automatically open, the crew will take action to manually open 2SWP*MOV77A

& 77B per N2-SOP-11 Note: The crew may choose to place the mode switch in shutdown during the course of the event based on operator judgment.

This is an acceptable action and will not prevent

When intake bay level lowers to 234 feet, determines 2SWP*MOV77A

& 77B failed to open automatically and manually opens them.

Determines intake bay level is rising and informs the SRO. SRO

Acknowledges report of rising intake bay level. evaluation of the critical task nor interfere with the remaining events in this scenario.

Event 1 *

c.;teria NRC Scenario 2

2SWP*MOV77A and 77B open

Service Water Intake Bay level rising Page 25 of 42 CENG_ 8JOI'1t venture of---, 0=--.;,eDF I NINE MILE POINT NUCLEAR STATION Events #6 and #7: Loss of Feed Pumps and Level Control Issues .Event Information

A Loss of feed pumps will occur.

The crew will use alternate level control systems to maintain RPV water level Note: If the crew placed the mode switch in shutdown in the previous event, the below malfunctions were inserted:

RR20, DBA LOCA, FV=1.5, RT=15:00 FW03A, FEED PUMP TRIP (P1A) FV=TRUE FW03B, FEED PUMP TRIP (P1B) FV=TRUE, DT=3 When directed by lead evaluator, insert the following malfunction:

TRG6 RR20, DBA LOCA, FV=l.S, RT=15:00 FW03A, FEED PUMP TRIP (P1A) FV=TRUE FW03B, FEED PUMP TRIP (P1B) FV=TRUE, DT=3 Feed Pumps A and B trip OW pressure starts to rise slowly RPV water level starts to lower NRC Scenario 2 Page 26 of 42 a JOint venture of---, 0=""""'" -;:,eDF I NINE MILE POINT NUCLEAR STATION The following annunciators alarm:

603139, REACTOR WATER LEVEL HIGH/LOW

851509, REACTOR FEED PUMP 1A/18/1C AUTO TRIP

851519, REAC FEED PMP 1A/1B/1C MOTOR ELEC FAULT

851523, CNST BSTR PMP 2A/2B/2C SUCTION FLOW LOW

851546, CNST PUMP DISCH HEADER FLOW LOW

851254, PROCESS AIRBORNE RADN MON ACTIVATED CREW

Recognizes and reports loss of feed pumps and rising drywell pressure SRO

Acknowledges report of loss of feed pumps and rising drywell pressure.

Directs the RO to place the mode switch in shutdown.

RO

Acknowledges direction to place the mode switch to shutdown.

Places mode switch to shutdown .

Provides scram report to SRO Page 27 of 42 NRC Scenario 2 a jOint ventureol-----, 0=:',_ <t,eoF I NINE MILE POINT NUCLEAR STATION NRC Scenario 2 SRO

Acknowledges scram report

Enters N2-EOP-RPV on low RPV water level

Directs RO to perform actions of N2-SOP-101C

Directs RO to maintain RPV water level 160 to 200 inches using any one or a combination of the following injection sources: 0 Feed Pump by starting Feed Pump C 0 Maximize RDS Flow per N2-0P-30, H.3.0 0 RCIC 0 HPCS o Condensate Booster Pumps (requires a pressure reduction)

Directs BOP to maintain RPV Pressure 800 to 1000 psig with the EHC system or to coordinate with RO to maintain 500 to 600 psig with EHC to facilitate booster pump injection.

RO CN2-SOP-101Cl

Acknowledges direction to take actions per N2-SOP-101C

Acknowledges direction to maintain RPV water level 160 to 200 inches using 0 Feed Pump by starting Feed Pump C 0 RDS Flow per N2-0P-30, H.3.0 0 RCIC 0 HPCS 0 Condensate Booster Pumps

Performs initial actions of N2-SOP-101C:

o Verifies turbine has tripped and TSV/TCVs are shut Page 28 of 42 CENG .. aJOI'll venture oi---, 0=-

I NINE MILE POINT NUCLEAR STATION Role Play As PO directed to energize 2WCS-MOV107, acknowledge the report. Note: The starting of Feed Pump C may or may not be performed based on the level control strategy selected by the SRO. NRC Scenario 2 RO (cont.) o Verifies generator has tripped and house loads have transferred o Verifies SDV vent and drain valves have closed o Verifies RCS pumps have downshifted o As necessary inserts SRMs and IRMs 0 Determines scram cannot be reset due to high drywell pressure 0 Places all FWLC Valves to MANUAL and verifies all FWLC Valves are fully shut 0 May direct energizing 2WCS-MOV107 0 May shutdown HWC RO {N2-SOP-101C-Start Feed PumR C)

Attempts to start Feed Pump C per N2-SOP-101C as follows: 0 Determines at least one condensate pump is available 0 Places Feed Pump A and B control switches in Pull To Lock 0 Determines at least two condensate pumps and two condensate booster pumps are already running. 0 Places the FWLC Master and individual controllers in MANUAL and shuts all FWLC valves. 0 Determines that it is not required to reset the Level 8 trips. 0 Confirms Feed Pump C suction is >500 psig o Verifies Feed Pump C Aux Oil Pump is running. Page 29 of 42 a JOict vectuce of I 0

-!'eOF NINE MILE POINT NUCLEAR STATION When the RO places the Feed Pump C switch to start, verify inserted the following malfunction:

TRG7 FW03C, FEED PUMP TRIP (PlC) FV=TRUE, DT=lS After 15 seconds, Feed Pump C trips Note: The maximizing of RDS Flow may or may not be performed based on the level control strategy selected by the SRO. When the RO places the RDS Pump lB switch to start, verify inserted the following malfunctions:

TRGS RD12A, CRD FEED PUMP TRIP (PlA) FV=TRUE RD12B, CRD FEED PUMP TRIP (PlB) FV=TRUE, DT=3 RDS Pumps P1A and P18 trip. Note: Use of HPCS may or may not be performed based on the level control strategy selected by the SRO. NRC Scenario 2 o Places Feed Pump C control switch to START o Confirms Feed Pump C starts when the minimum flow valve is tv19% open. o Opens Feed Pump C FWLC Valve and injects to maintain RPV Level 160 to 200 inches. o Recognizes and reports that Feed Pump C has tripped on motor electric fault and that Feed Pump C is not available.

RO CN2-0P-30

-Maximize RDS flow)

Attempts to maximize RDS Flow as follows: o Determines that both RPS A and Bare tripped. o Verifies RDS Pump lA is already running. o Places RDS Pump lB control switch in START o Recognizes and reports that both RDS Pumps have tripped on motor electric fault and are not available RO (Starting HPCS -N2-0P-33l

Starts HPCS as follows: o If not already initiated due to Level 2 or high drywell pressure, ARM's and DEPRESSES the HPCS MANUAL INITIATION PUSHBUTTON.

o Verifies HPCS Pump starts o Verifies HPCS Injection Valve opens o Verifies HPCS Minimum Flow Valve closes on rising HPCS flow Page 30 of 42 CENG,. a JO<OI 'ectuce ot I

"';,*,eoF NINE MILE POINT NUCLEAR STATION Role Play If contacted as PO to perform running checks on the Division 3 EDG, wait two minutes and inform the control room that running checks have been completed satisfactorily NRC Scenario 2 o Verifies Division 3 EDG starts. o At 2CEC*PNL851, verifies open 2CNS-AOV123, CONDENSATE STORAGE TKS MAKE UP VLV o OPENS and SHUTS HPCS Injection Valve as necessary to maintain RPV Water Level 160 to 200 inches. RO (Starting RCIC -N2-EOP-HC}

Initiates RCIC as follows: o If RCIC is not already running, arms AND depresses RCIC MANUAL INITIATION pushbutton o Verifies the following:

GLAND SEAL SYSTEM AIR COMPRESSOR starts

ICS*MOV116 opens

ICS*MOV120 opens

ICS*MOV126 opens

WHEN RCIC flow >220 gpm, ICS*MOV143 closes

WHEN RCIC discharge pressure > Reactor pressure, ICS*V156 AND ICS*V157 open

RCIC injection to Reactor controlled at 600 gpm

ICS*AOV109 closes

ICS*AOV110 closes

ICS*AOV130 closes

ICS*AOV131 closes o Controls RCIC as follows:

If maintained in Automatic Control, maintains Turbine Speed >1500 rpm and Injection Flow between 400 to 600 gpm. Page 31 of 42

a pnt 'enturo of I NINE MILE POINT NUCLEAR STATION Note: Use of Condensate Booster Pumps for injection may or may not be performed based on the level control strategy selected by the SRO. If this strategy is selected, then an RPV pressure reduction will be required to allow booster pumps to inject. RO (cont.)

If maintained in manual Control, maintains Turbine Speed >1500 rpm and Injection Flow <600 gpm. o If it is desired to reject RCIC to the CST (i.e. tank to tank mode), performs the following:

Opens 2ICS*MOV124, TEST BYPASS TO CON. STORAGE TANK

Throttles 2ICS*FV108 TEST BYPASS TO CON. STORAGE TANK as necessary to control RPV Level. BOP (Lowering RPV Pressure for Inject.)

Acknowledges direction to maintain RPV pressure 500 to 600 psig using EHC.

Coordinates with RO and lowers RPV pressure as follows: o DEPRESSES the INCREASE pushbutton for the BYPASS OPENING JACK until 5 bypass valves indicate full open o Adjusts the bypass valves as necessary to control RPV Pressure 500 to 600 psi g. RO (Injecting with Cond. Booster Pumps)

Coordinates with BOP to lower RPV pressure and injects with Condensate Booster Pumps as follows: o As RPV pressure lowers, opens LV10A, B, orCas required to maintain RPV level 160 to 200 inches. o May place FWLC back into automatic.

Page 32 of 42 NRC Scenario 2 CENG .. a JO""entuce of I NINE MILE POINT NUCLEAR STATION * .. Terll',tination NRC Scenario 2 BOP {N2-SOP-101C-Pressure Control}

Acknowledges direction to maintain RPV pressure 800 to 1000 psig using EHC.

As necessary to control pressure, performs the following:

0 Closes 2MSS-AOV87A/B/C/D and AOV88A/B 0 Closes 2ASS-MOV152 o Starts 2ARC-P1A or B as follows:

Confirms there is no fuel damage

Closes 2ARC-AOV104

Places in AUTO 2ARC-AOV105

Opens SWP-HV98A(B)

Starts 2ARC-P1A(B)

Verifies proper operation o Closes 2ASS-MOV148 o As necessary to prevent excessive cooldown, closes the MSIV's. SRO

As required, acknowledges report of trip of Feed Pump C and RDS Pumps.

Adjusts level control and pressure control strategies as appropriate based on equipment malfunctions.

RPV Level Control has been established.

RPV Pressure Control has been established.

Page 33 of 42 a JO'" 'ectu'e ot I O=:'IIIUon NINE MILE POINT NUCLEAR STATION Event #8 and #9: LOCA with failure of PC Spray Systems Event lnf4)rmation

A LOCA will occur causing drywell pressure to rise.

The crew will respond and attempt to mitigate Primary Containment parameters, however due to failure of the spray systems, a blowdown will eventually be required due to PSP. Note: The following malfunction was inserted in the previous event: RR20, DBA LOCA, FV=l.S, RT=15:00 Based on the level and pressure control strategies chosen by the crew, the rate of drywell pressure rise may rise or lower. As determined by the lead evaluator, the severity value on the above malfunction may be modified as necessary to raise or lower the rate of drywell pressure rise. A few minutes after the initiation of the previous event, the following additional annunciators alarm:

603140, DRYWELL PRESSURE HIGH/LOW

603101, RPS A DRYWELL PRESSURE HIGH TRIP

603401, RPS 8 DRYWELL PRESSURE HIGH TRIP NRC Scenario 2 Crew

Recognizes and reports rising drywell pressure.

BOP

Recognizes and reports that Division 1 ECCS Systems failed to automatically initiate

ARMs and DEPRESSES the Division 1 ECCS Manual Initiation Pushbutton.

Page 34 of 42 a JO""entuce of I

..:,eDF NINE MILE POINT NUCLEAR STATION Note: A malfunction will prevent manually starting of RHS Pump lA. Role Play If directed to investigate the cause of why RHS Pump lA would not start and/or directed to locally shut the RHS Pump lA breaker, wait two minutes and inform the control room that there is nothing visibly wrong with the pump and breaker but you were not able to get the breaker to shut locally. BOP (cont.)

Determines that the initiation pushbutton failed to operate.

Manually starts the LPCS pump by placing the control switch to START

Attempts to manually start RHS Pump lA

Determines RHS Pump lA will not start from the control room.

May dispatch an operator to investigate cause and/or locally shut the RHS Pump lA breaker.

Reports to the SRO that RHS Pump lA failed to start. SRO CN2-EOP-PC)

Acknowledges report of rising drywell pressure and that RHS Pump lA failed to start.

Enters N2-EOP-PC and reenters N2-EOP-RPV when drywell pressure reaches 1.68 psig.

Determines drywell pressure cannot be maintained below 1.68 psig.

Determines Suppression Pool water level is below 217 feet.

Directs BOP to spray the suppression chamber using RHS B per N2-EOP-6.22

As necessary, directs RO/BOP to start a 5th Service Water Pump

As necessary, directs RO/BOP to restore pneumatics to the Drywell. Page 35 of 42 NRC Scenario 2 a JOint venture of 0 =:n-kJn I NINE MILE POINT NUCLEAR STATION NRC Scenario 2 ROlBOP (N2-EOP-HC

-5th SW PumR)

Acknowledges direction to start a 5th Service Water Pump

Starts a Service Water Pump as follows: o Selects either SWP E or F to start o Verifies 2SWP*MOV74 shut for the associated pump. o Starts SWP Pump lE or lF by placing its associated control switch to START o Verifies the associated MOV47 opens.

Reports to the SRO that a 5th Service Water Pump has been started. ROlBOP (N2-EOP-HC Restore Pneum.)

Acknowledges direction to restore pneumatics to the Drywell

Restores pneumatics to the Drywell as follows: o At 2CEC*PNL851:

Places LOCA OVERRIDE VLV IAS*SOV166 to OVERRIDE

Opens IAS*SOV166 o At 2CEC*PNL851:

Places LOCA OVERRIDE VLV IAS*SOV184 to OVERRIDE

Opens IAS*SOV184 o At 2CEC*PNL601:

Places LOCA OVERRIDE VLV IAS*SOV164 to OVERRIDE

Opens IAS*SOV164 o At 2CEC*PNL601:

Places LOCA OVERRIDE VLV IAS*SOV165 to OVERRIDE

Opens IAS*SOV165

Informs the SRO that pneumatics have been restored to the drywell. Page 36 of 42 a JOint venture of---, 0=:---

I NINE MILE POINT NUCLEAR STATION Role Plax As RP contacted to place RE-23B in service, wait two minutes and insert the following remote function : TRG9 RM02-041, SWP 23B RAD MONITOR ONLINE, FV=ON RM03-041, SWP 23B RAD MONITOR SAMPLE PUMP POWER, FV=ON Report back to control room that RE-23B is in service NRC Scenario 2 BOP CN2-EOP-6.22l

Acknowledges direction to spray the suppression chamber using RHS B

Sprays the suppression chamber using RHS Bas follows: 0 Determines a LOCA Signal is present and drywell pressure is >1.68 psig. 0 Opens 2SWP*MOV90B o Verifies closed and overridden 2RHS*MOV24B o Verifies running RHS*P1B o Sprays the suppression chamber by opening 2RHS*MOV33B o Verifies >450 gpm on the suppression chamber spray flow meter. o Throttles 2SWP*MOV33B as necessary to supply Service Water Flow of rv7400 gpm to the RHS B Heat Exchanger.

0 Contacts RP and directs them to start 2SWP*RE23B

Informs the SRO that RHS Pump 1B is spraying the suppression chamber SRO CN2-EOP-PCl

Acknowledges report of RHS Pump 1B spraying the suppression chamber

Waits until suppression chamber pressure reaches 10 psig

Page 37 of 42 a JO'n"enturo of I 0 =:n.uan et,eoF NINE MILE POINT NUCLEAR STATION Note: Unless Drywell Unit Coolers have been restored per N2-EOP-6.24, the coolers should already be tripped. NRC Scenario 2 SRO (cont.)

Determines suppression pool water level is still below 217 feet

Determines parameters or within the Drywell Spray Initiation Limit

Directs the RO/BOP to trip both recirculation pumps

Directs the RO/BOP to trip all drywell unit coolers.

Directs BOP to spray the drywell with RHS Pump lB. ROlBOP (TriR Recirculation PumRS)

Acknowledges direction to trip the Recirculation Pumps

If not already completed, trips the Recirculation Pumps as follows: 0 Places Control Switch(s) for Recirculation Pumps A and B to STOP

Informs the SRO that Recirculation Pumps A and B are tripped. ROlBOP (Drxwell Unit Coolers)

Acknowledges direction to verify tripped all Drywell Unit Coolers

Verify tripped all Drywell Unit Coolers as follows: o At 2CEC*PNL873, observes that all red running lights for all drywell coolers are off.

Informs SRO that all drywell coolers are verified tripped. BOP (N2-EOP-6.22)

Acknowledges direction to spray the drywell using RHS B

Sprays the drywell using RHS Bas follows: Page 38 of 42

a joint venture of---, 0=--;:,eDF I NINE MILE POINT NUCLEAR STATION Note: When attempting to spray the drywell, MOV25B will fail to open due to it being stuck shut. Role Play As PO directed to attempt to open 2RHS&MOV25B, wait 3 minutes and inform the control room that it is stuck shut and you are getting additional operators to help you open the valve. BOP (cont.) 0 Determines drywell spray interlocks are met o Verifies open 2SWP*MOV90B o Verifies closed 2RHS*FV38B o Verifies running RHS Pump lB o Verifies 2RHS*MOV33B is open o Verifies >450 gpm on the suppression chamber spray flow meter. o Attempts to spray the drywell by opening 2RHS*MOV15B and 2RHS*MOV25B 0 Recognizes that 2RHS*MOV25B will not open. 0 Dispatches a PO to attempt to manually open 2RHS*MOV25B o Informs the SRO that the he cannot spray the drywell using RHS Pump lB. SRO CN2-EOP-PC)

Acknowledges report of the inability to spray the drywell using RHS Pump lB

Directs the BOP to spray the drywell using Fire Water through RHS A per N2-EOP-6.6

Analyzes the Pressure Suppression Pressure curve.

Determines he cannot restore and maintain suppression chamber pressure and suppression pool water level within the Pressure Suppression Pressure limits.

Enters N2-EOP-C2, RPV Slowdown Page 39 of 42 NRC Scenario 2 CENG,. a JOint venture of---, o=--lon I NINE MILE POINT NUCLEAR STATION Role Play As PO directed to lineup Firewater to RHS A, acknowledge report. Note; this action will not be completed prior to the end of the scenario.

If contacted for updates, acknowledge the request and inform the control room that you are still working on getting the lineup completed.

NRC Scenario 2 BOP CN2-EOP-6.6l

Acknowledges direction to spray the drywell using Firewater through RHS A

Sprays the drywell using Firewater through RHS A as follows: o Starts Firewater Pump 1 or 2 o Determines RHS A is not in operation o Places RHS Pump 1A in Pull To Lock o Verifies closed the following valves:

RHS*MOV15A, OUTLET TO DRYWELL SPRAY

RHS*MOV25A, OUTLET TO DRYWELL SPRAY

RHS*MOV33A, OUTLET TO SUPPR POOL SPRAY

RHS*FV38A, RETURN TO SUPPR POOL COOLING

RHS*MOV24A, LPCI A Injection VLV

RHS*MOV40A, SDC A Return

RHS*MOV12A, HEAT EXCHANGER 1A OUTLET VLV o If possible, verifies closed RHS*MOV8A, HEAT EXCHANGER 1A INLET BYPASS VLV o Directs a PO to lineup Firewater to RHS A per N2-EOP-6.6, Starting on Step 6.1.6 SRO CN2-EOP-C2l

Enters N2-EOP-C2, RPV Blowdown:

o Determines Reactor will stay shutdown without boron o Determines drywell pressure is above 1.68 psig Page 40 of 42 a JOirll venture of 0=---!'>eDF I NINE MILE POINT NUCLEAR STATION Note: Based on the chosen level control strategy, the SRO may choose to prevent injection with some or all low pressure ECCS Pumps. CT-2.0: Given Suppression Chamber Pressure unable to be restored and maintained within the Pressure Suppression Limit, the crew will open 7 SRV's lAW N2-EOP-C2 CT-2.0: Given Suppression Chamber Pressure unable to be restored and maintained within the Pressure Suppression Limit, the crew will open 7 SRV's lAW N2-EOP-C2 NRC Scenario 2 SRO (cont.) o As necessary based on Level Control strategy, directs RO/BOP to prevent LPCS and LPCI injection.

o Determines suppression pool level is >192 feet o Directs BOP to open 7 ADS valves. RO/BOP (Prevent LPCS/LPCIInjectionl

Acknowledges direction to prevent LPCS and LPCI Injection

As required, prevents LPCS and LPCI Injection as follows: o If necessary, places LPCS in PTL. o Verifies shut and overridden the following valves:

RHS*MOV24B, LPCI B Injection VLV

RHS*MOV24C, LPCI C INJECTION VLV

Informs the SRO that LPCS and LPCI Injection has been prevented BOP CN2-EOP-HC

-Blowdownl

Acknowledges direction to open 7 ADS valves and performs the following:

o Determines no SRVs are stuck open and an ECCS pump is running o Arms and depresses both ADS pushbuttons for each division o Informs the SRO that 7 ADS valves are open Page 41 of 42 CENG .. a pot veotuce of I -t,eDF NINE MILE POINT NUCLEAR STATION Event .

. NRC Scenario 2

7 SRVs are open SRO CN2-EOP-RPV)

Acknowledges report from BOP that 7 ADS valves are open

RPV Pressure is lowering Page 42 of 42 1\liNE MILE POINT NUCU:AR . Training Id: NRC 2013 Scenario 4 Copy of __ Revision:

0.0 -----Title: SCl-Secondary containment leak. Blowdown Required.

Signature I Printed Name Developed By David Huff Validated By Michael Storms Phil MacEwen Doug Mizener Facility Reviewer " Aaron Armstrong Page 1 of 34 NRC Scenario 4 NiNE MILE POINT NUCLEAR STATION References

1. N2-0P-101A, Reactor Startup 2. N2-0P-30, Control Rod Drive System 3. N2-SOP-60, Loss of Drywell Cooling 4. N2-SOP-19, Loss of Instrument Air 5. N2-0P-31, Residual Heat Removal System 6. N2-SOP-90, Natural Events 7. N2-EOP-RPV, RPV Control 8. N2-EOP-SC, Secondary Containment Control 9. N2-EOP-C2, RPV Blowdown 10. Unit 2 Technical Specifications Page 2 of 34 NRC Scenario 4 CENG .. NINE MILE POINT NUCLEAR S 1A110N Instructor Information A. Scenario Description The crew will take the shift at tv3% power. The RO will raise power using rods. While withdrawing rods, a control rod will stick. The crew will take action to raise drive water pressure per N2-0P-30.

Raising drive water pressure will free the stuck rod and allow the startup to continue.

After power has been sufficiently raised, an instrument failure will cause one pair of Suppression Chamber to Drywell Vacuum Breakers to fail open. There are no operator actions; however the CRS will evaluate TS 3.6.1. 7. Once TS 3.6.1. 7 has been evaluated, an electrical fault will cause a loss of all drywell cooling. The crew will respond per N2-SOP-60 and restart the drywell cooling fans in "Fan Only" mode. After Drywell Cooling has been restored, an electrical fault will occur on Instrument Air Compressor A. Compressors Band C will fail to auto start. The crew will take action per N2-SOP-19 and manually start either Compressor B or C (CRITICAL TASK) to restore air header pressure.

After the loss of instrument air, a failure will cause a spurious initiation of Division 1 ECCS systems. Additionally, the minimum flow valve for RHS Pump A will fail to open leaving RHS Pump A without minimum flow protection.

The crew will take action to shutdown the Division 1 ECCS systems. The CRS will evaluate TS 3. 5.1 and 3.8.1. Following the inadvertent initiation of Division 1 ECCS systems, a seismic event occurs. The event will cause an unisolable RCIC steam leak and a FWLC failure. The crew will take action per N2-EOP-SC and enter N2-EOP-RPV to manually scram the reactor (CRITICAL TASK). RPV level control will be complicated by the FWLC failure. Due to the RCIC steam leak, Secondary Containment conditions will continue to degrade requiring the Page 3 of 34 NRC Scenario 4 NOTES CENG, a JOI'I\ venture oi J 0 =:*latlon NINE MILE POINT NUCLEAR STATION crew to either anticipate RPV blowdown per N2-EOP-RPV, or perform a blowdown per N2-EOP-C2 (CRITICAL TASK). The scenario may be terminated when the RPV is being depressurized.

1. Termination Criteria a. RPV is being depressurized.

2. Critical Tasks NOTES CT-1.0 Justification:

This task is identified as critical because without operator action to start the lag or backup air compressor, instrument air header pressure will degrade until the reactor scrams due to low RPV level and/or loss of scram air header pressure.

a. CT-1.0, Given a trip of the running instrument air compressor and a failure of the lag and backup air compressors to automatically start, the crew will take action to manually start the lag or backup air compressor.

CT-2.0 Justification:

This task is identified as critical because without operator action to scram, the reactor will continue to provide energy to the RCIC steam line break and cause increased secondary containment temperatures and radiation levels. b. CT-2.0, Given secondary containment temperatures approaching a maximum safe value in one area, the crew will initiate a manual reactor scram lAW N2-EOP-RPV Page 4 of 34 NRC Scenario 4 CENG .. NINE MILE POINT NUCLEAR STATION I NOTES CT-3. OA Justification:

This task is identified as critical because without operator action to depressurize the reactor, secondary containment integrity, the integrity of equipment located in the secondary containment, and continued safe operation of the plant cannot be assured. Note: The crew may choose to wait until two or more areas are above maximum safe values before depressurizing the reactor. If the crew chooses to depressurize the reactor via the SRVs, then CT-3.0A does not have to be evaluated.

c. CT-3.0A, Given secondary containment temperatures approaching or above maximum safe values in one area, the crew will open 5 main turbine bypass valves IAW N2-EOP-RPV CT-3.08 Justification:

This task is identified as critical because without operator action to depressurize the reactor, secondary containment integrity, the integrity of equipment located in the secondary containment, and continued safe operation of the plant cannot be assured. Note: The crew may choose to "anticipate blowdown" and depressurize the reactor to the main condenser.

If the crew chooses to depressurize the reactor to the main condenser and are successful in preventing two areas from exceeding the maximum safe temperatures, then CT-3. 08 does not have to be evaluated.

d. CT-3.08, Given secondary containment temperatures above maximum safe values in two areas, the crew will open 7 ADS valves IAW N2-EOP-C2

3. Length a. rv7Q minutes 4. Mitigation Strategy Code a. SC1-Secondary containment leak. Slowdown Required 5. Technical Specifications

a. TS 3.6.1.7 b. TS 3.5.1 c. TS 3.8.1 6. EAL Classification

a. Site Area Emergency, FS1.1, Loss or potential loss of ANY two fission product barriers.

Page 5 of 34 NRC Scenario 4 CENG, ClJOin1 venture o'---J

-;:,eOF NINE MILE POINT NUCLEAR STATION b. Table F-1, RCS Barrier Loss C3 and C4, Potential Loss C1 c. Table F-1, Containment Barrier Loss C3. 7. Special Orders a. None B. Initial Conditions

1. IC Number a. IC-153 2. Presets I With Triggers a. Malfunctions

1) IA04A, LAG COMPRESSOR AUTO START FAILURE, FV=TRUE 2) IA04B, B/U COMPRESSOR AUTO START FAILURE, FV=TRUE 3) RC11, RCIC ISOLATION FAILURE, FV=TRUE 4) PClOA, DRYWELL VACUUM BKR PAIR FAIL OPEN (2ISC*RV33A/B), FV=TRUE 5) PCOl, LOSS OF DRYWELL COOLING, FV=TRUE 6) IA02A, 2IAS-C3A THERMAL OVERLOAD TRIP, FV=TRUE 7) RH13A, ECCS INADVERTENTLY INITIATES (DIV 1), FV=TRUE 8) RH15, RHS*MOV4A VALVE FAILS SHUT, FV=TRUE 9) MTOl, SEISMIC ACCELERATION, FV=2 10) FWOSB, LV55B FAILURE-CLOSED, FV=TRUE 11) RC12, RCIC STEAM LEAK IN RB, FV=35, RT=15:00 Page 6 of 34 NRC Scenario 4 NOTES INSERTED INSERTED INSERTED TRGl TRG2 TRG3 TRG4 TRG4 TRGS TRGS TRGS CENG. n J01'1t venture of J 0 .. uon ...:::eoF NINE MILE POINT NUCLEAR STATION 12) RD07-26-43, ROD 26-27 STUCK, FV=TRUE b. Remotes 1) None c. Overrides

1) 01A2S041DI0365, ICS*MOV121 SWITCH CLOSE, FV=OFF 2) 01A2S041DI0366, ICS*MOV121 SWITCH OPEN, FV=OFF 3) 01A2S042DIOS64, ICS*MOV128 SWITCH CLOSE, FV=OFF 4) 01A2S042DI0418, ICS*MOV128 SWITCH OPEN, FV=OFF d. Annunciators

1) None e. Event Triggers Event # Event Action 10 RDVPOSB(137)==160 (Rod 26-43 at position 10) 11 hzardr602>0.863 (Drive Water DP greater than 300 psid) f. Equipment Out of Service 1) None g. Support Documentation

1) Turnover Sheet and RMI 2) N2-0P-101A marked up to step E.3.4 3) A2 Startup Rod Sequence marked up to RWM Step 15, Rod 18-27 Page 7 of 34 NRC Scenario 4 NOTES TRG10 INSERTED INSERTED INSERTED INSERTED Command Blank dmf RD07-26-43 NINE MILE POINT NUCLEAR STATION h. Other 1) Ensure that when IC-153 is loaded, the RWM latches on to RWM step 15, Rod 14-35 and there are no RWM rod blocks 2) Ensure the rod position plaque is posted with position 12 on it. Page 8 of 34 NRC Scenario 4 NOTES CENGN NINE MILE POINT NUCLEAR STATION SHIFT TURNOVER INFORMATION ON COMING SHIFT: o N I D DATE: _,Tc...::o=d=-ay,___

__ PART I: To be performed by the oncoming Operator before assuming the shift.

Control Panel Walkdown (all panels) (SRO, ROs) PART II: To be reviewed by the oncoming Operator before assuming the shift.

LCO Status (SRO)

Shift Turnover Information Sheet Evolutions/General Information/Equipment Status:

Reactor Power is 3%

A Reactor Startup is in progress

RPV Pressure is 925 psig with 1 bypass valve partially open

Feed Pump B is running with level control on LV55B

A reactor startup in progress per N2-0P-1 01A. Currently on step E.3.4. The Clean Steam Reboiler is still on the Aux Boilers per SM direction.

The SM wants to complete an inspection on an aux steam component prior to transferring the Reboiler to aux steam. Once the inspection is complete, the SM will inform the control room.

Currently on A2 Up startup sequence, RWM Step 15, rod 18-27 withdrawing control rods from position 8 to position 12

All LCOs are met PART Ill: Remarks/Planned Evolutions:

Raise reactor power using rods per the startup rod sequence and provided RMI to 8% in preparation for transferring the mode switch to run. RE and STA are available in the control room. Page 9 of 34 NRC Scenario 4 I CENG. NINE MILE POINT NUCLEAR ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver:

Reactor Startup Step: A2 Startup INITIAL CONDITIONS/STEP DESCRIPTION RE presence required in the Control Room?

No --If YES above, RE presence not required for steps Initial conditions to be verified prior to initiation of step: Parameter Expected Range Actual Parameter Expected Range Core Flow 20 to 59 Mlb/hr 28 Mlb/hr RWM A2 Sequence Time Today Today Description of Step: Actual A2 CD Perform Reactor Startup in accordance with A2 startup sequence and appropriate procedures Critical parameters to be monitored DURING Step:

not used must be deleted OR marked N/A Critical Limit Owner Frequency Contingency Parameter SRM Count 3 RO Continuous when SRMs Single Notch Withdrawal Rates doublings inserted Rx Period 60 sec RO Continuous when SRMs Insert last control rod one notch inserted I RMI evaluated against approved power profile:

N/A D. I Other Comments:

None Step Prepared By: Joe Engineer Today Step Reviewed By: John Engineer Today REIST A Date RE/STA/SRO Date Approval to Perform Step: Joe Manager Today Shift Manager Date Step Completed By: SRO Date Page 10 of 34 NRC Scenario 4 I I o JOint venture of J 0 =:'latton NINE MILE POINT NUCLEAR STATION Shift Turnover Instructor Actions I Plant Response Take the Simulator out of freeze before the crew enters for the pre-shift walkdown.

Verify annunciator sound turned on

If recording scenario, start the recording device during the pre-shift walkdown Allow no more than 5 minutes to walkdown the panels. NRC Scenario 4 Operator Actions Crew

Walkdown panels

Conduct shift turnover brief

Assume the shift Page 11 of 34 CENG, ajOI'Itventureof J 0

-;:,eDF NINE MILE POINT NUCLEAR STATION Events #1 and 2, Withdraw rods to raise power and one rod sticks. Event Information

Initial reactor power is 3%.

The crew will withdraw rods to raise power

One control rod will stick. The crew will raise drive water pressure to free the stuck control rod. SRO

Directs RO to raise reactor power to 8% using the A2 startup rod sequence and provided RMI RO

Acknowledges direction to raise power using control rods

Monitors RPV, CRD and Nuclear Instruments

Withdraws control rods lAW rod sequence using single notch withdrawal.

Note:

Determines and reports rod 26-43 is stuck When rod 26-43 is moved from position 8 to at position 10 position 10, verify the following malfunction is inserted:

TRG10 RD07-26-43, ROD 26-43 STUCK, FV=TRUE SRO

Acknowledges report that rod 26-43 is stuck at position 10 Role Plax

May contact SM/RE for direction If contacted as the SM/RE for direction, inform

Directs RO to respond to the stuck rod per them to follow the appropriate procedures for N2-0P-30.

a rod which fails to withdraw.

Page 12 of 34 NRC Scenario 4 NINE MILE POINT NUCLEAR STATION Note: Do to variations in drive water flow indications, the crew may determine that the insert portion of the DCV sequence is operating correctly and continue on H.1.2. If the crew determines the insert portion of the DCV sequence is operating correctly, then they will refer to section H.1.1 to continue trying to free the stuck rod. The actions are relatively the same, so either action is acceptable.

Note: When drive water pressure is raised above 300 psid, verify deleted the following malfunction:

RD07-26-43, ROD 26-27 STUCK Note: Once rod 26-43 has been withdrawn to position 12, the Lead Evaluator may choose to either continue the startup to 8%, or may move on to the next event. RO

Acknowledges direction to respond to the stuck control rod per N2-0P-30

References section H.1.2, Failure to Withdraw Using Single Notch Withdrawal.

Attempts to withdraw rod 26-43 again while monitoring drive water flow

Determines one of the following:

o Drive water flow was not approximately 4 GPM during the insert portion of the rod withdrawal. -OR-o Drive water flow was approximately 4 GPM during the insert portion of the rod withdrawal.

May refers to section H.1.1, Failure to Insert

Raises drive water pressure 50 psid by throttling shut on 2RDS-PV101

Attempts to INSERT/WITHDRAW rod 26-43 one notch

Determines rod 26-43 inserted/withdrew one notch

Lowers drive water pressure back to 260 psid

Withdraws rod 26-43 to position 12 if necessary.

Page 13 of 34 NRC Scenario 4 CENGW a JOI'lt venture of J NINE MILE POINT NUCLEAR STATION Event Termination Criteria NRC Scenario 4

Control Rod 26-43 has been freed

Reactor power has been raised sufficiently as determined by the Lead Evaluator.

Page 14 of 34

8. JOint venture of J NINE MILE POINT NUCLEAR STATION Event #3: One Pair of Drywell Vacuum Breakers Fail Open Event Information

One pair of Drywell to Suppression Chamber Vacuum Breakers will fail open. No operator action is required.

The SRO will evaluate per TS 3.6.1.7 Note: At the lead evaluator's discretion, this event may be initiated concurrently with the next event. When directed by the lead evaluator, insert the following malfunction:

TRGl PClOA, DRYWELL VACUUM BKR PAIR FAIL OPEN (2ISC*RV33A/B), FV=TRUE 2ISC*RV33A and B fail open Drywe/1 and Suppression Chamber pressure equalize.

The following annunciator alarms:

601556, DRYWELL VACUUM BRKR INBOARD DISC OPEN

601557, DRYWELL VACUUM BRKR OUTBOARD DISC OPEN Crew

Recognizes and reports AN601556 and AN 601557 SRO

Acknowledges report of annunciators

Directs BOP to respond per the ARPs Page 15 of 34 NRC Scenario 4

" JOI'lt venture of J NINE MILE POINT NUCLEAR STATION Role Play As the SM, acknowledge the report of the failure of the vacuum breakers and inform the SRO that you will contact maintenance and the work week manager. Event Termination Criteria

TS 3.6.1.7 referenced.

BOP

Acknowledges direction to respond per the ARPs.

References ARP 601556 and 601557 .

Determines that both 2ISC*RV33A and B indicate open on 2CEC*PNL628.

Informs the SRO that there are no additional actions which can be taken per the ARPs and that both 2ISC*RV33A and Bare open. SRO

Acknowledges report of 2ISC*RV33A and B being open.

References TS 3.6.1.7, Conditions Band C and determines he has two hours to close at least one of the open vacuum breakers and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to close the remaining one.

Contacts SM and informs him of the vacuum breaker failures.

Page 16 of 34 NRC Scenario 4 CENG.o ilJOI'lt venture oi J -t::eoF NINE MILE POINT NUCLEAR STATION Event #4: Loss of Drywell Cooling Event Information

An instrumentation fault will cause a loss of drywell cooling.

The crew will respond per N2-SOP-60 and restart Drywell Cooling Fans in "Fans Only" mode. Note: At the discretion of the lead evaluator, this event may be imitated concurrent with the previous event. When directed by lead evaluator, insert the following malfunction:

TRG2 PCOl, LOSS OF DRYWELL COOLING, FV=TRUE All drywell unit coolers trip off Drywell temperature slowly starts to rise The following annunciators alarms:

873201 DRYWELL UNIT COOLING GROUP 1 SYS TROUBLE

873202 DRYWELL UNIT COOLING GROUP 2 SYS TROUBLE

873304 DIVISION I DRYWELL TEMPERATURE HIGH CREW

Recognizes and reports loss drywell cooling. SRO

Acknowledges report of the loss of drywell cooling

Directs BOP to enter N2-SOP-60 Page 17 of 34 NRC Scenario 4 CENG, il )Ornt venture of J 0 NINE MILE POINT NUCLEAR STATION Note: The amber light for DIVISION I DRYWELL UNIT COOLER COOLING WATER manual isolation will be lit on 2CEC*PNL602.

If the crew recognizes this, they will be able to make the determination immediately that the drywell cooling valves will not be able to be reopened.

If this is the case, they may continue only in the fan leg of N2-SOP-60.

NRC Scenario 4 BOP CN2-SOP-60l

Acknowledges direction to enter N2-SOP-60

Informs SRO that N2-SOP-60 directs monitoring of drywell temperature and pressure

Determines Division I drywell cooling valves are closed

Attempts to restore drywell cooling using the cooling leg of N2-SOP-60

May determine that drywell cooling valves cannot be opened based on 2CEC*PNL602 DIVISION I DRYWELL UNIT COOLER COOLING WATER manual isolation amber light being lit and continue in the Fan leg of N2-SOP-60

Attempts to re-open Drywell Cooling Isolation valves as follows: o Places DRYWELL UNIT COOLER WTR DIV I LOCA OVERRIDE switch in OVERRIDE o Closes the CCP inlet isolation valves for all drywell unit coolers o Attempts to re-open 2CCP*MOV265 AND MOV124 o Determines and reports that valves will not reopen

Continues in the fan only leg of N2-SOP-60

Restores drywell fans as follows: o Places the following switches in OVERRIDE:

UNIT COOLER FANS GRl LOCA OVERRIDE

UNIT COOLER FANS GR2 LOCA OVERRIDE Page 18 of 34 NINE MILE POINT NUCLEAR STATION Role Play As the SM, acknowledge the report of the loss of drywell cooling and inform the SRO that you will contact maintenance and the work week manager. BOP Ccont.l o Starts the following DRS Unit Cooler Fans:

2DRS-UC1A

2DRS-UC1B

2DRS-UC1C

2DRS-UC1D

2DRS-UC2A

2DRS-UC2B

2DRS-UC2C

2DRS-UC2D

2DRS-UC3A

Reports drywell fans are restored SRO

Acknowledges report of drywell fans restored.

Contacts SM and informs him of the loss of Drywell Cooling Event Termination Criteria

Drywell cooling fans restored in the "Fan's Only" Mode. Page 19 of 34 NRC Scenario 4 CENG., NINE MILE POINT NUCLEAR STATION Event #5: Loss of Instrument Air Event Information

The running instrument air compressor trips and the lag and backup compressors fail to auto start.

The crew will respond per N2-SOP-19 and start either the lag or backup air compressors.

Verify inserted the following malfunctions:

IA04A, LAG COMPRESSOR AUTO START FAILURE, FV=TRUE IA04B, B/U COMPRESSOR AUTO START FAILURE, FV=TRUE When directed by lead evaluator, insert the following malfunction:

TRG3 IA02A, 2IAS-C3A THERMAL OVERLOAD TRIP, FV=TRUE IAS-C3A trips on thermal overload Standby CCP Mini-Loop Pump Auto Starts lAS Header Pressure begins to lower The following annunciators alarm:

INSTR AIR CPSR 3A/38/3C AUTO TRIP/FAIL TO START

INST AIR COMPRESSOR CLG WTR FLOW LOW

851260, INST AIR COMPRESSOR COOLING SYS TROUBLE NRC Scenario 4 CREW

Recognizes and reports trip of 2IAS-C3A SRO

Acknowledges trip of IAS-C3A

Directs BOP to enter N2-SOP-19 Page 20 of 34 NINE MILE POINT NUCLEAR STATION Role Play If dispatched as a PO to monitor lAS pressures, use Simulator Computer Screen IA01 to monitor and report pressures as required by the control room. Note: The BOP may wait until lAS pressure lowers to 100 psig and observing IAS-C3B did not auto start before taking manual action to start a backup air compressor -or-the BOP may choose to manually start a backup air compressor before the failure of the backup air compressor to auto start is apparent.

Either action is acceptable.

CT-1.0, Given a trip of the running instrument air compressor and a failure of the lag and backup air compressors to automatically start, the crew will take action to manually start the lag or backup air compressor.

lAS Air Header Pressure begins to rise. BOP

Acknowledges direction to enter N2-SOP-19

May dispatch POs to monitor the following lAS pressures:

o 2IAS-PI194, (RB 261') o 2RDS-PI133, (RB 261')

Determines an air compressor has tripped.

Determines the loss of air compressor was not due to a slow transfer or loss of control power

Manually starts IAS-C3B orCas follows: o Places lAS Compressor Selector Switch to either BCA or CAB o Places IAS-C3B or 3C control switch in START o Verifies IAS-C3B or 3C starts and lAS Air Header pressure is rising.

Informs the SRO that IAS-C3B or 3C is running and that lAS Air Header Pressure is rising.

Refers to Attachment 1 of N2-SOP-19 SRO

Acknowledges report from BOP that lAS Air Header Pressure has been restored.

Page 21 of 34 NRC Scenario 4 a JOI'lt venture oi J 0 =:nation NINE MILE POINT NUCLEAR STAfiON Role Plav As the SM, acknowledge the report of the loss of instrument air and inform the SRO that you will contact maintenance and the work week manager. SRO {cont.)

Contacts SM and informs him of the loss of Instrument Air Event Termination Criteria

IAS-C3B or 3C is running

Instrument Air Header pressure is rising Page 22 of 34 NRC Scenario 4 CENG, NINE MILE POINT NUCLEAR STATION Event #6: Spurious Initiation of Division 1 ECCS Systems Event Information

A spurious initiation of Division 1ECCS Systems will occur with a failure of RHS A Pump Minimum Flow Valve to Open.

The crew will take action to secure the Division 1 ECCS Systems. When directed by lead instructor/evaluator, insert the following malfunction:

TRG4 RH13A, ECCSINADVERTENTLY INITIATES (DIV I), FV=TRUE RH15, RHS*MOV4A VALVE FAILS SHUT, FV=TRUE Division 1 ECCS Systems and diesel automatically start The following annunciators alarm:

601413, LPCS PUMP 1 AUTO START

601426, LPCS SYSTEM ACTUATED

601442, RHR PUMP 1A AUTO START

601451, RHR A SYSTEM ACTUATED

601539, ADS A LPCS / RHR A PERMISSIVE

852109, DIVISION I EDG 1 START SYSTEM TROUBLE

852117, EDG 1 RUNNING CREW

Recognizes and reports inadvertent initiation of Division 1 ECCS Systems SRO

Acknowledges report of Division 1 ECCS Systems running.

Directs the BOP to respond per the ARPs Page 23 of 34 NRC Scenario 4 a JOint venture of--] 0 NINE MILE POINT NUCLEAR S fATION Role Plax: If requested to provide RHR and CSL trip unit indications (2CEC*PNL629), report that no trip units are in alarm and that no gross failures are present. Note: At this time, there is no requirement to attempt to shutdown the remaining Division 1 ECCS Systems. The SRO may choose to wait to shutdown the systems until after he has had a chance to talk with the SM. This is an acceptable action. If the SRO waits until after he contacts the SM, a role play from the SM will direct the SRO to shutdown the remaining Division 1 ECCS Systems per the appropriate OP's. NRC Scenario 4 BOP

Acknowledges direction to respond per the ARPs.

References ARP for 601413 and 601442

Determines by looking at multiple indications that RPV Level is not below Level 1 and Drywell Pressure is not above 1.68 psig.

Informs the SRO that there are no valid initiation signals for Division 1 ECCS Systems.

Reviews the automatic response of Division 1 ECCS systems and determines and reports 2RHS*MOV4A did not open

Attempts to manually open 2RHS*MOV4A

Determines 2RHS*MOV4A did not open and informs the SRO SRO

Acknowledges report of no valid Division 1 ECCS Initiation signal and 2RHS*MOV4A failing to open

Directs BOP to place RHS Pump 1A in Pull to Lock.

May direct BOP to also attempt to shutdown the remaining Division 1 ECCS Systems Page 24 of 34 ajOI'ltvcntureoi J 0 =:'I*Uon NINE MILE POINT NUCLEAR STATION Role Play As directed to perform running checks on Division 1 EDG, wait 2 minutes and inform the control room that running checks have been completed satisfactorily.

Role Play As the booth, if contacted for any trip units, inform the operator that there are no trip units tripped. BOP

Acknowledges report to place RHS Pump 1A in Pull To Lock

Places RHS Pump 1A control switch in Pull To Lock

As required, acknowledges direction to shutdown the remaining Division 1 ECCS Systems.

Dispatches PO to perform running checks on Division 1 EDG.

May contact the booth and ask for any trip units which may have actuated.

As required, performs a shutdown of the LPCS system per N2-0P-32 as follows: 0 Depresses LPCI A/LPCS RESET pushbutton.

0 Determines white reset seal-in light did not extinguish 0 Places LPCS pump control switch in Pull to Lock

As required, performs a shutdown of the Division 1 EDG per N2-0P-100A, Section H.16.0 as follows: 0 Places EMERGENCY DSL GEN 1 LOCA SIGNAL BYPASS switch to ON 0 Places DIVISION 1 2EGS*EG1 START switch in PULL-TO-LOCK

Informs the SRO that the Division 1 ECCS Systems are shutdown.

SRO

Acknowledges report of RHS Pump 1A control switch in Pull to Lock.

As required, acknowledges report of Division 1 ECCS Systems Page 25 of 34 NRC Scenario 4 a)OI'lt venture of--]

NINE MILE POINT NUCLEAR STATION Role Play As the SM, acknowledge the report of the Division 1 ECCS System Failure and inform the SRO that you will contact maintenance and the work week manager. If the SRO has not already shutdown the Division 1 ECCS Systems, direct the SRO to attempt to shutdown or place the systems in PTL per the appropriate OPs. Note: Because the Division 1 ECCS systems are inoperable, the SRO cannot use the extended 14 day completion time allowed per Condition B. He is required to use the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time as references in the TS 3.8.1 Bases. SRO Ccont.l

Contacts SM and informs him of the Division 1 ECCS System Failure

If necessary, acknowledges direction to shutdown the remaining Division 1 ECCS Systems.

Refers toTS 3.5.1 and determines that with both LPCS and RHS A inoperable that Condition A and C applies and he has 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore one of the pumps to operable status and 7 days to restore the remaining pump.

Refers toTS 3.6.1.6 and determines that Condition A applies and he has 7 days to restore RHS A drywell spray system to operable status.

Refers toTS 3.6.2.3 and determines Condition A applies and he has 7 days to restore RHS A suppression pool cooling to operable status

Refers toTS 3.8.1 and determines Condition B applies and that he must perform SR 3.8.1.1 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restore the Division 1 EDG to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Event Termination Criteria

Division 1 ECCS Systems are shutdown NRC Scenario 4

SRO has referenced Technical Specifications, (At the Lead Evaluator's discretion, the referencing of all Tech Specs may be deferred until after the end of the scenario as long as appropriate follow up questions are used at the completion of the scenario).

Page 26 of 34 CENG .. aJOI'lt venture of--] 0 =:nation NINE MILE POINT NUCLEAR STATION Event #7, 8, and 9: Seismic Event, FWLC Failure, RCIC Steam Leak Event Information

A seismic will occur which will cause a FWLC Failure and RCIC Steam Leak

The crew will respond per N2-EOP-RPV, EOP-SC, and EOP-C2 to mitigate the event. Note Ensure several instructors are staged to shake the back of panels in conjunction with inserting the next malfunction to simulate an earthquake When directed by the Lead Evaluator, insert the following malfunctions and shake the back of several panels: TRGS MTOl, SEISMIC ACCELERATION, FV=2 FWOSB, LVSSB FAILURE -CLOSED, FV=TRUE RC12, RCIC STEAM LEAK IN RB, FV=35, RT=15:00 RPV Level begins to lower RB Temperatures begin to rise The following annunciator alarms:

603139, REACTOR WATER LEVEL HIGH/LOW After a few minutes, the following additional annunciators alarm:

601157, REACTOR BLDG GENERAL AREAS TEMP HIGH

602218, DIVISION 1 NSSSS !SOL SIGNAL

602224, DIVISION 2 NSSSS !SOL SIGNAL NRC Scenario 4 Page 27 of 34 CENG .. aJOI"tventureof--J o=:**ation NINE MILE POINT NUCLEAR STATION Note: Although the SRO may direct entry into N2-SOP-06, the actions directed by N2-SOP-06 for this FWLC failure are time consuming and will not be able to be completed prior to the RCIC steam leak requiring a reactor scram. Role Play As PO contacted to provide indications on the Seismic Monitor Panel, wait 2 minutes and inform them that an amber light is lit on the Response Spectrum Annunciator section CREW

Recognizes and reports seismic event RO

Recognizes that FW LVSSB has drifted full shut and that RPV level is slowly lowering

Places LVSSB in MANUAL control and adjusts the valve to maintain RPV Level in the normal band.

Informs the SRO that LVSSB failed and it is manual control SRO

Acknowledges report of a seismic event and FWLC failure

Directs BOP to enter N2-SOP-90

May direct RO to enter N2-SOP-06 BOP CN2-SOP-90)

Acknowledges direction to enter N2-SOP-90

Review plant process computer and determines ERSNC02 computer point is in and determines the plant has exceeded the OBE

May contact PO and direct them to provide indications at the Seismic Monitor Panel

Informs the SRO that N2-SOP-90 requires a plant shutdown per N2-0P-101C Page 28 of 34 NRC Scenario 4 CENG. aJOI'ltventureol J 0 NINE MILE POINT NUCLEAR STATION Role Play As POs contacted to perform walkdowns, acknowledge report. Wait 5 minutes and inform them that there appears to be a steam leak in on RB215 in the RCIC Pipe Chase Role Play As Unit 1 and JAF Control Rooms, respond that you did also feel the earthquake.

Role Play As PO dispatched to place service water strainers in continuous backwash, wait 5 minutes and inform the control room that all operating pump strainers are in continuous backwash Role Play As I&C, acknowledge the direction to perform N2-IMP-ERS-001 Role Play As Maintenance, acknowledge direction to perform N2-MSP-Y001 BOP {cont.)

Contacts POs and directs them to perform plant walkdowns of the following areas: o ECCS Pump Rooms o ECCS Piping o Refuel Floor/ Spent Fuel Pool o Emergency Switchgear/Diesels o Pipe Tunnel

Contacts Unit 1 and JAF Control Rooms to communicate receipt of Seismic Event Indications

Directs PO to place all service water pump discharge strainers in continuous backwash in accordance with N2-0P-11, H.3.0

Notifies I&C TO PERFORM N2-IMP-ERS-001, Post Event Data Retrieval

May refer to N2-0P-86, Section H.l.O to verify operability of Loose Parts Monitor

Informs SRO to refer to TRM 3.3.7.2 and 3.7.6

Contacts Maintenance and directs them to perform N2-MSP-V001 RO CN2-SOP-06l

Acknowledges direction to enter N2-SOP-06

Reviews N2-SOP-06 and determines the following additional actions can be taken: o Swap Feed Pumps o Place LV10B in service

Informs the SRO of the options for dealing with the FWLC failure. Page 29 of 34 NRC Scenario 4 NINE MILE POINT NUCLEAR STATION Note: As RCIC pipe chase temperature rises above 135F, WCS will isolate but RCIC will not isolate as expected.

NRC Scenario 4 Crew

Recognizes and reports high RB temperatures SRO

Acknowledges report of high RB temperature

Enters N2-EOP-SC on RB area temperature above an isolation setpoint

Directs RO to evacuate the RB

Directs BOP to monitor RB temperatures RO

Acknowledges direction to evacuate the Reactor Building

Makes GAITRONICS announcement to evacuate the Reactor Building BOP

Acknowledges direction to monitor RB Temperatures

Monitors RB temperatures and determines WCS system isolated and RCIC system should have isolated

Informs the SRO that RCIC should have isolated

Attempts to manually isolate RCIC by taking the following keylock switch to shut on P601: o 2ICS*MOV128 o 2ICS*MOV121

Reports to SRO that RCIC failed to isolate manually Page 30 of 34 ajOI'lt venture o1--J NINE MILE POINT NUCLEAR STAfiON CT-2.0 Given secondary containment temperatures approaching a maximum safe value in one area, the crew will initiate a manual reactor scram lAW N2-EOP-RPV CT-2.0 Given secondary containment temperatures approaching a maximum safe value in one area, the crew will initiate a manual reactor scram lAW N2-EOP-RPV NRC Scenario 4 SRO

Acknowledges report of RCIC failing to isolate automatically and manually

Determines a primary system is discharging into the RB

Determines one RB area is approaching a maximum safe value

Enters N2-EOP-RPV and directs RO to place the mode switch in shutdown RO

Acknowledges direction to place the mode switch in shutdown

Places mode switch in shutdown

Provides scram report to the SRO SRO

Acknowledges scram report

Directs RO to enter N2-SOP-101C

Directs RO to maintain RPV water level 160 to 200 inches using feed and condensate

Directs RO to maintain RPV pressure 800 to 1000 psig using EHC Page 31 of 34 CENG" a)OI!"It ventu-eof--J NINE MILE POINT NUCLEAR STATION Role Play As Radwaste, acknowledge the direction to operate all pumps for 2DER-TK2A Role Play As PO directed to energize 2WCS-MOV107, acknowledge the report. NRC Scenario 4 RO

Acknowledges direction to: 0 Enter N2-SOP-101C 0 Maintain RPV water level 160 to 200 inches using feed and condensate 0 Maintain RPV pressure 800 to 1000 psig using EHC

Performs initial actions of N2-SOP-101C:

o Verifies SDV vent and drain valves have closed

May determine the scram can be reset and attempt to reset the scram as follows: 0 Notifies Radwaste to operate all pumps for 2DER-TK2A. 0 Places all four SDV high level bypass switches to bypass. 0 Using scram reset switches, reset the scram and verifies all 8 pilot solenoid lights lit

Maintains RPV water level 160 to 200 inches using feed and condensate

As necessary inserts SRMs and IRMs

May direct energizing 2WCS-MOV107

May shutdown HWC

Maintains RPV pressure 800-1000 psig using EHC BOP

Continues to monitor RB temperatures .

Determines and reports a second RB area temperature is rising and approaching a maximum safe value Page 32 of 34 CENG. NINE MILE POINT NUCLEAR S fATION Note: At this point the SRO may make the decision to "Anticipate Blowdown" CT-3.0A Given secondary containment temperatures approaching or above maximum safe values in one area, the crew will open 5 main turbine bypass valves lAW N2-EOP-RPV Note: If the evaluation team would like to see the crew enter N2-EOP-C2, then at the discretion of the Lead Evaluator, modify the following malfunction as necessary to cause a second area temperature to go above the maximum safe value: RC12, RCIC STEAM LEAK IN RB CT-3.0A Given secondary containment temperatures approaching or above maximum safe values in one area, the crew will open 5 main turbine bypass valves lAW N2-EOP-RPV Note: The BOP should continue to monitor temperatures until he verifies all RB temperatures are lowering.

If a second area temperature goes above a maximum safe value, then a blowdown MUST be performed per N2-EOP-C2 and Critical Task 3.0B must be evaluated NRC Scenario 4 SRO <Anticipate Blowdownl

Acknowledges report of second RB area temperature approaching a maximum safe value

Directs the RO to open 5 main turbine bypass valves RO

Acknowledges direction to open 5 main turbine bypass valves

Using the Bypass Opening Jack Increase Pushbutton, opens 5 bypass valves

Informs the SRO that 5 bypass valves are open BOP

Continues to monitor RB temperatures

If temperatures continue to rise, informs the SRO that a second area temperature is above the maximum safe value Page 33 of 34 CENG. a J01'1t venture of J NINE MILE POINT NUCLEAR STATION CT-3.0B Given secondary containment temperatures above maximum safe values in two areas, the crew will open 7 ADS valves lAW N2-EOP-C2 CT-3.0B Given secondary containment temperatures above maximum safe values in two areas, the crew will open 7 ADS valves lAW N2-EOP-C2 SRO

Acknowledges report of a second area temperature above a maximum safe value

Enters N2-EOP-C2

Determines the reactor will stay shutdown without boron

Determines drywell pressure is < 1.68 psig

Determines suppression pool level is above 192 feet

Directs BOP to open 7 ADS valves BOP

Acknowledges direction to open 7 ADS valves.

Determines no ECCS pump is running

Takes control switches to OPEN at BOTH 2CEC*PNL628 and 2CEC*PNL631 UNTIL a total of 7 SRVs are open: o MSS*PSV137 o MSS*PSV127 o MSS*PSV126 o MSS*PSV121 o MSS*PSV134 o MSS*PSV130 o MSS*PSV129

Reports to the SRO that 7 ADS valves are open. Event Termination Criteria

RPV depressurization in progress

Secondary containment temperatures lowering Page 34 of 34 NRC Scenario 4

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